Tritium production module system, gas-cooled reactor, tritium system and combined system of gas-cooled reactor and fusion reactor

Abstract

Disclosed in the present invention is a tritium production module system in a reactor. The tritium production module system has a multi-layer structure distributed in the radial direction of the reactor, and the tritium production module system comprises a tritium production area and a circulation area, wherein the tritium production area comprises a tritium breeding material, the tritium breeding material interacting with neutrons to produce tritium elements; the tritium production module system is in fluid communication with the outside of the tritium production module system via the circulation area; the circulation area comprises a tritium pipeline, the tritium pipeline being used for circulation of a reactor coolant and a tritium-containing medium, and the tritium pipeline extending in the axial direction of the reactor; a plurality of holes are provided in a pipe wall of the tritium pipeline, and the tritium pipeline is in fluid communication with the tritium production area via the holes, thereby improving the ability and efficiency of tritium transfer in the tritium production module system.

Description

Tritium production module system, gas-cooled reactor, tritium system, and combined system of gas-cooled reactor and fusion reactor Technical Field

[0001] The present invention relates to the field of reactor technology, and in particular to a tritium production module system, a gas-cooled reactor, a tritium system, and a combined system of a gas-cooled reactor and a fusion reactor. Background Art

[0002] Currently, the main objectives of gas-cooled reactor research and design, both domestically and internationally, include nuclear power generation, power generation, and hydrogen production. Gas-cooled reactors have a higher proportion of high-energy neutrons, resulting in a higher core neutron leakage rate and a harder neutron spectrum than water-cooled reactors. This requires a larger fuel load, a higher fissile nuclide enrichment, and a more hostile neutron irradiation environment. Neutrons leaking from the core, particularly fast neutrons with energies above 0.1 MeV and 1.0 MeV, not only cause radiation damage to reactor internals and pressure vessels, but also, as the cumulative neutron dose increases, affect the mechanical properties of these equipment. This accelerates the aging of critical equipment, such as pressure vessels, and significantly increases the significant safety risk of embrittlement, fracture, and failure. Furthermore, neutrons leaking from the core of a gas-cooled reactor increase radiation levels outside the reactor, posing a risk to personnel and equipment. Therefore, it is necessary to install neutron moderation and reflection materials such as graphite in the core or its periphery, or to increase the thickness of the reactor shielding or use materials with stronger shielding properties. However, these measures will significantly increase the size, weight, and cost of the gas-cooled reactor. If a functional component for tritium production is installed in the gas-cooled reactor, this problem can be effectively solved.

[0003] In addition, a major problem faced by fusion reactors and fusion-fission hybrid reactors designed at home and abroad is tritium self-sustainability. The tritium breeding ratio (TBR) analysis values ​​of various engineering experimental fusion reactors or fusion-fission hybrid reactors currently designed and developed are all below 1.2 (inclusive), and fusion-fission hybrid reactors are generally lower than fusion reactors. In fact, tritium at high temperatures can penetrate the barrier of the tritium collection system, resulting in a certain proportion of loss. At the same time, under the current level of technology, it is difficult to collect, purify and treat tritium to the level of theoretical analysis and design. In addition to the above factors, the loss of tritium during storage and handling must also be considered. Therefore, it is difficult to achieve true "tritium self-sustainability" in engineering practice.

[0004] The prior art CN115440394A discloses a tritium-producing blanket, which includes a first wall, a sleeve, a neutron multiplier container and a shielding plate. The shielding plate is supported on one side of the vacuum chamber, and the neutron multiplier container is supported on the side of the shielding plate away from the vacuum chamber. The first wall is sleeved on the outside of the neutron multiplier container, and the free end of the first wall is fixedly connected to the shielding plate by welding. The sleeve is located inside the neutron multiplier container, and multiple sleeves are distributed at intervals inside the neutron multiplier container.

[0005] The prior art CN103578574A discloses a tritium-producing blanket for a fusion-fission subcritical energy reactor core, comprising several layers of tritium-producing material, with moderator water provided between two adjacent layers of tritium-producing material, a zirconium separator provided between the tritium-producing material and the moderator water, and a zirconium cladding provided outside the tritium-producing blanket.

[0006] None of the above technical solutions are applicable to gas-cooled reactors, and the transfer capacity and efficiency of tritium elements in the tritium-producing blanket need to be improved.

[0007] Prior art CN103578579A discloses a loading scheme for a fusion-fission subcritical energy reactor core. The core structure includes several fuel assembly modules arranged circumferentially along an annular plasma fusion region. Each fuel assembly module includes several fuel assemblies arranged poloidal to the plasma fusion region. A high-temperature and radiation-resistant first wall is arranged on the side of each fuel assembly facing the plasma fusion region. A tritium-producing blanket is arranged on the other side of each fuel assembly relative to the first wall. An outer shield is provided outside the tritium-producing blanket.

[0008] Prior art CN114171233A discloses a device for online tritium production and recovery in a reactor. The device consists of an irradiation tritium production unit, an online tritium extraction unit, an exhaust gas purification and emergency tritium recovery unit, and a tritium monitoring unit. The irradiation tritium production unit is installed in the reactor core and connected to the online tritium extraction unit via a carrier gas pipeline. This device is applicable to various reactors and enables rapid and efficient online tritium production and recovery. However, this technical solution is not designed for gas-cooled reactors and does not address the tritium self-sustaining problem of fusion reactors.

[0009] Currently available designs are unable to achieve effective tritium production in gas-cooled reactors, enhance the tritium-carrying capacity of the gas medium within them, or effectively address the tritium sustainability challenge in fusion and fusion-fission hybrid reactors. There are no devices or systems that can sustainably and stably supply tritium and helium-3, or other fusion fuels, to fusion or fusion-fission hybrid reactors. There is also no integrated system that can achieve mutual fuel supply (fusion and fission) between gas-cooled fission reactors and fusion or fusion-fission hybrid reactors.

[0010] In view of the above technical problems, the present invention is specially introduced.

[0011] Summary of the Invention

[0012] The main purpose of the present invention is to provide a tritium production module system, a gas-cooled reactor, a tritium system, and a combined system of a gas-cooled reactor and a fusion reactor, so as to enable the gas-cooled reactor to achieve a better tritium production effect and enhance the tritium carrying capacity of the gas medium in the gas-cooled reactor. In addition, the combined system can also solve the tritium self-sustaining problem of the fusion reactor.

[0013] To achieve the above-mentioned purpose, a tritium-producing module system is proposed, which is arranged inside a reactor. The tritium-producing module system has a multi-layer structure distributed radially along the reactor. The tritium-producing module system includes a tritium-producing area and a circulation area. The tritium-producing area includes tritium breeding material, which reacts with neutrons to produce tritium elements. The tritium-producing module system is fluidically connected to the outside of the tritium-producing module system through the circulation area. The circulation area includes a tritium pipe, which is used for the circulation of reactor coolant and tritium-containing medium. The tritium pipe extends along the axial direction of the reactor. A plurality of holes are opened on the wall of the tritium pipe, and the tritium pipe is fluidically connected to the tritium-producing area through the holes.

[0014] Furthermore, the tritium pipeline is a multi-layer pipeline, and a plurality of holes are opened on the pipe wall of any layer or any multiple layers of the multi-layer pipeline.

[0015] Furthermore, the tritium pipeline is a 2-3 layer pipeline and holes are opened on the pipe wall of each layer of the pipeline. From the outer layer to the inner layer of the tritium pipeline, the number of holes increases layer by layer.

[0016] Furthermore, the tritium production module system includes a coolant inlet, the coolant inlet includes a fluid acceleration device, and the fluid acceleration device is connected to the tritium pipeline.

[0017] Furthermore, the fluid acceleration device is a structure with a changing cross-sectional area, and the fluid acceleration device includes a contraction section, or a contraction section, a narrow throat section and an expansion section connected in sequence along the flow direction. The cross-sectional area of ​​the contraction section changes from large to small along the flow direction, and the cross-sectional area of ​​the expansion section changes from small to large along the flow direction.

[0018] Furthermore, the tritium production module system also includes a cladding and a tritium production layer group. The cladding is arranged at intervals along the radial direction of the reactor. The tritium production layer group is located between the claddings. The tritium production layer group includes a tritium breeding layer and / or a tritium breeding multiplication layer. The tritium pipeline is at least partially located in the tritium production layer group.

[0019] Furthermore, the tritium-producing layer group includes a neutron multiplying layer and a tritium breeding layer arranged along the radial direction of the reactor, the tritium breeding layer is located outside the neutron multiplying layer, and the tritium pipeline is at least partially located inside the tritium breeding layer.

[0020] Furthermore, the tritium-producing module system also includes a partition, which is located between different types of layers in the tritium-producing layer group; the tritium-producing module system also includes an anti-tritium permeation layer, which is adjacent to the cladding and adopts a coating or a low-permeability structure. The anti-tritium permeation layer includes oxides and titanium-containing ceramics, and the oxides include one or more of the following substances: Cr2O3, Al2O3, and Ti2O2.

[0021] Furthermore, the tritium production module system also includes a reflection layer or a moderator layer, and the material of the reflection layer or the moderator layer includes one or more of the following substances: graphite, isostatic graphite, nuclear-grade graphite, boron carbide, silicon carbide, boron-containing silicon carbide, beryllium oxide or beryllium-containing compounds.

[0022] Furthermore, the tritium production module system also includes an irradiation product production layer, and the materials of the irradiation product production layer include one or more of the following substances: Np-237 and its compounds for producing Pu-238, Co-59 and its compounds for producing Co-60, and partitions are set on both sides of the irradiation product production layer.

[0023] Furthermore, the tritium production module system includes a cladding, a tritium penetration prevention layer, a neutron multiplication layer, a partition, a tritium breeding layer, a partition, an irradiation product production layer, a partition, a reflection layer or a moderation layer, a tritium penetration prevention layer, and a cladding, which are arranged in sequence from the inside to the outside along the radial direction of the reactor.

[0024] Furthermore, the tritium-producing layer group includes a first circulation structure, in which the neutron multiplying layers and tritium breeding layers arranged along the radial direction of the reactor circulate multiple times; or the tritium-producing layer group includes a second circulation structure, in which any arrangement and combination of the neutron multiplying layers, tritium breeding layers and tritium breeding multiplication layers arranged along the radial direction of the reactor circulate multiple times.

[0025] Furthermore, the tritium-producing layer group includes a tritium multiplication layer, which includes a neutron multiplication section and a cylindrical tritium multiplication section. Multiple tritium multiplication sections are evenly arranged in the neutron multiplication section, and the volume ratio of the neutron multiplication section to the tritium multiplication section is in the range of 2:1 to 8:1. The tritium pipes are arranged in an array in the tritium multiplication section.

[0026] Furthermore, the tritium production module system is shaped like a circular column and completely surrounds the periphery of the reactor core in the circumferential direction. The tritium production module system is composed of multiple tritium production sub-modules in the circumferential direction, and the number of tritium production sub-modules is in the range of 4 to 24.

[0027] Furthermore, the neutron multiplying layer includes a neutron multiplying material ball, which contains a neutron multiplying material, and the neutron multiplying material includes beryllium and beryllium-containing compounds; the tritium breeding layer includes a tritium breeding material ball, which contains a tritium breeding material, and the tritium breeding material includes one or a mixture of the following substances: Li2O, Li2TiO3, LiAlO2, Li4SiO4, and Li2ZrO3 ceramics.

[0028] Further, the tritium multiplication layer includes a neutron multiplication material ball and a tritium multiplication material ball; or the tritium multiplication layer includes a tritium multiplication material ball, the core part of the tritium multiplication material ball has tritium multiplication material, and the shell part of the tritium multiplication material ball has neutron multiplication material.

[0029] Furthermore, the enrichment of Li-6 in the tritium breeder material is 7.5% to 90%, the enrichment of Li-7 is 10% to 92.5%, and the total enrichment of Li-6 and Li-7 is 100%; the tritium breeder material with a Li-7 enrichment of 50% to 92.5% is arranged at a position close to the reactor core, and the tritium breeder material with a Li-6 enrichment of 50% to 90% is arranged at a position far away from the core.

[0030] Furthermore, the neutron multiplying layer, the tritium breeding layer and the tritium breeding multiplying layer all include a tritium producing layer group air inlet, and the tritium producing layer group air inlet is provided with a support structure and a first filter screen for preventing the material in the tritium producing layer group from leaking out.

[0031] Furthermore, a second filter screen or filter membrane is provided on the inner side or outer side of the wall of the tritium pipeline to prevent materials or dust in the tritium-producing layer group from entering the tritium pipeline.

[0032] By applying the above technical solution of the present invention, at least the following beneficial effects are achieved:

[0033] 1. This tritium production module system is equipped with a fluid acceleration device at the coolant inlet to increase the flow rate of the tritium medium in the tritium production module system. This allows the flow rate, pressure, and density of the gas medium entering different structural layers of the tritium production module system to be different, thereby enhancing the ability and efficiency of the gas medium to carry tritium. At the same time, the ultrasonic vibrations generated can remove tritium deposited and attached to the walls of the flow channel in the tritium production module system, thereby reducing tritium sedimentation losses.

[0034] 2. This tritium production module system makes it easier for tritium to be released and diffused into the tritium pipeline by arranging the tritium pipeline into multiple layers and opening holes in the pipeline wall, as well as setting the number of holes. In addition, the tritium pipeline is connected and coordinated with the fluid acceleration device, so that the airflow rate in the tritium pipeline increases layer by layer and the pressure decreases layer by layer from the outer layer to the inner layer, thereby further enhancing the efficiency of tritium release and diffusion from the tritium production area to the tritium pipeline.

[0035] 3. This tritium production module system can better realize the functions of neutron multiplication and tritium production by setting up a neutron multiplying layer, a tritium breeding layer structure or a tritium breeding multiplying layer structure, and improve the tritium production rate by allocating positions with different abundances of Li-6 and Li-7. By using a gas-cooled reactor to produce tritium, the radiation hazard to reactor components and external personnel and equipment caused by neutron leakage from the high core of the gas-cooled reactor is resolved, and the thickness of the gas-cooled reactor's reflector layer, moderator layer and external shielding body can be reduced.

[0036] 4. This tritium production module system provides a support structure and a first filter at the air inlet of the tritium production layer group to allow the gas medium to enter and prevent the leakage of materials in the tritium production module system; and provides a second filter or filter membrane on the inner or outer side of the pipe wall of the tritium pipeline to prevent or reduce the entry of materials or dust in the tritium production layer group into the tritium pipeline, and also prevent graphite dust and other impurities in the core from entering the tritium production module system.

[0037] 5. This tritium production module system is completely surrounded by the reactor in the circumferential direction and is composed of a certain number of tritium production daughter modules, so that the reactor can achieve the maximum tritium production effect. When a part of the tritium production daughter modules has problems, it is convenient to replace them, thereby ensuring the stability of the reactor's tritium production.

[0038] To achieve the above objectives, a gas-cooled reactor is proposed, comprising a tritium production module system, which is arranged outside the core of the gas-cooled reactor and produces tritium elements by interacting with neutrons in the core.

[0039] Furthermore, the gas-cooled reactor includes a core, a nuclear fuel sealing isolation layer and a reactor pressure vessel arranged from the inside to the outside along its radial direction, and the tritium production module system is located between the nuclear fuel sealing isolation layer and the reactor pressure vessel.

[0040] Furthermore, the nuclear fuel sealing isolation layer includes a metal container or a panel, and also includes a fixed support structure.

[0041] Furthermore, the gas-cooled reactor also includes a neutron regulating layer, which includes a first neutron regulating layer, a second neutron regulating layer and a third neutron regulating layer, and the neutron regulating layer includes a coolant flow channel and / or a neutron multiplying layer and / or a reflective layer and / or a moderating layer.

[0042] Furthermore, a second neutron regulation layer is provided between the nuclear fuel sealing isolation layer and the tritium production module system.

[0043] Furthermore, a third neutron regulation layer is provided between the reactor pressure vessel and the tritium production module system.

[0044] Furthermore, a first neutron regulating layer is provided between the core and the nuclear fuel sealing isolation layer.

[0045] By applying the above technical solution of the present invention, at least the following beneficial effects are achieved:

[0046] 1. The gas-cooled reactor can produce tritium by setting up a tritium production module system outside the core, which can solve the radiation hazard of neutron leakage from the high core of the gas-cooled reactor to reactor components and external personnel and equipment, and can also reduce the thickness of the gas-cooled reactor's reflector layer, moderator layer and external shielding body.

[0047] 2. By setting up neutron regulation layers on both sides of the tritium production module system and between the core and the nuclear fuel sealing isolation layer, the gas-cooled reactor can improve the utilization rate of core neutrons in the gas-cooled reactor and improve the tritium production efficiency; by changing the structure of the neutron regulation layer, it can adapt to gas-cooled reactors of different types and different states.

[0048] To achieve the above-mentioned objectives, a tritium system is proposed, comprising a tritium production module system and a tritium fuel supply system. The tritium production module system is connected to the tritium fuel supply system, and the reactor coolant and tritium-containing medium in the tritium production module system are input into the tritium fuel supply system to obtain tritium and / or helium-3 fuel, and the tritium fuel and / or helium-3 fuel are transported to the fusion reactor.

[0049] Furthermore, the tritium fuel supply system includes a tritium collection system, a tritium processing and storage system, and a tritium replenishment system connected in sequence. The tritium collection system is connected to the tritium production module system, and the tritium replenishment system is connected to the fusion reactor.

[0050] Furthermore, the tritium processing and storage system includes: a tritium extraction system, a tritium purification and separation system, a tritium storage system and a tritium monitoring system. The tritium monitoring system is respectively associated with the tritium extraction system, the tritium purification and separation system and the tritium storage system to monitor the equipment and facilities of each system.

[0051] Furthermore, the tritium collection system includes: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion / catalysis system.

[0052] Furthermore, the tritium replenishment system includes: a feed pretreatment system and a tritium injection system.

[0053] By applying the above-mentioned technical solution of the present invention, at least the following beneficial effects are achieved: the tritium system is provided with a tritium fuel supply system connected to the tritium production module system, and the tritium produced in the tritium production module system is collected, processed, stored and transported in the tritium fuel supply system, and tritium and / or helium-3 fuel can be delivered to the fusion reactor, thereby solving the problem of tritium self-sustaining and fuel replenishment of the fusion reactor.

[0054] In order to achieve the above-mentioned purpose, another gas-cooled reactor is proposed, including a core, a nuclear fuel sealing isolation layer and a reactor pressure vessel arranged from the inside to the outside along the radial direction of the gas-cooled reactor, and also including a tritium production module system. The tritium production module system is located on the periphery of the core and between the nuclear fuel sealing isolation layer and the reactor pressure vessel. The tritium production module system includes tritium breeding material, and the tritium breeding material reacts with neutrons generated by the core to produce tritium elements.

[0055] Furthermore, the gas-cooled reactor includes a reactor coolant inlet, a first gas acceleration device is provided at the reactor coolant inlet, and a gas medium physical parameter adjustment system is provided on the first gas acceleration device.

[0056] Furthermore, the gas medium physical parameter adjustment system includes multiple connecting pipes and valve assemblies. Multiple holes are opened on the wall surface of the air inlet section of the first gas acceleration device, which are respectively connected to the multiple connecting pipes. The valve assembly is arranged on the multiple connecting pipes, and the valve assembly includes a regulating valve, a constant pressure check valve and / or a variable pressure check valve.

[0057] Furthermore, the reactor coolant inlet is connected to the core and the tritium production module system respectively. The gas-cooled reactor includes a diverter plate, which is located between the first gas acceleration device and the core, and also between the first gas acceleration device and the tritium production module system. The diverter plate isolates the reactor coolant entering the core from the reactor coolant entering the tritium production module system.

[0058] Furthermore, the tritium production module system includes a tritium production module system coolant inlet, and the tritium production module system coolant inlet is provided with a second gas acceleration device; by adjusting the space between the diverter plate and the reactor pressure vessel, the intake volume and parameters of the reactor coolant entering the second gas acceleration device are adjusted, and the reactor coolant entering the tritium production module system is coupled with the second gas acceleration device.

[0059] Furthermore, the first gas acceleration device and / or the second gas acceleration device has a structure with a changing cross-sectional area, including a contraction section, or a contraction section, a narrow throat section and an expansion section connected in sequence along the direction of gas flow, the cross-sectional area of ​​the contraction section changes from large to small along the direction of flow, and the cross-sectional area of ​​the expansion section changes from small to large along the direction of flow.

[0060] Furthermore, the tritium-producing module system also includes a cladding and a tritium-producing layer group. The cladding is arranged at intervals along the radial direction of the gas-cooled reactor. The tritium-producing layer group is located between the claddings. The tritium-producing layer group includes a tritium breeding layer and / or a tritium breeding multiplication layer. The tritium breeding layer and the tritium breeding multiplication layer both include a tritium-producing region, and the tritium-producing region includes tritium breeding material.

[0061] Furthermore, the tritium-producing layer group also includes a tritium pipe for the circulation of reactor coolant and tritium-containing medium. The tritium pipe extends along the axial direction of the gas-cooled reactor, and a plurality of holes are opened on the pipe wall of the tritium pipe so that the inside of the tritium pipe is fluidically connected with the tritium-producing area.

[0062] Furthermore, the tritium-producing layer group includes a first neutron multiplying layer and a tritium breeding layer arranged radially along the gas-cooled reactor, the tritium breeding layer is located outside the first neutron multiplying layer, the first neutron multiplying layer includes neutron multiplying material, and the tritium pipeline is at least partially located in the tritium breeding layer.

[0063] Furthermore, the tritium-producing module system also includes partitions, which are arranged between different types of layers in the tritium-producing layer group and / or between the tritium-producing layer group and other layers; the tritium-producing module system also includes an anti-tritium permeation layer, which is adjacent to the cladding, and the anti-tritium permeation layer includes oxides and titanium-containing ceramics, and the oxides include one or more of the following substances: Cr2O3, Al2O3, Ti2O2.

[0064] Furthermore, the tritium production module system also includes an irradiation product production layer, and the materials of the irradiation product production layer include one or more of the following substances: Np-237 and its compounds for producing Pu-238, and Co-59 and its compounds for producing Co-60; partitions are arranged on both sides of the irradiation product production layer, and the irradiation product production layer is located on the outside of the tritium breeding layer.

[0065] Furthermore, the tritium production module system also includes a first reflection layer or a first moderator layer, which is located on the outside of the irradiation product production layer. The material of the first reflection layer or the first moderator layer includes one or more of the following substances: graphite, isostatic graphite, nuclear-grade graphite, boron carbide, silicon carbide, boron-containing silicon carbide, beryllium oxide or beryllium-containing compounds.

[0066] Furthermore, the tritium-producing layer group includes a tritium multiplication layer, which includes a neutron multiplication section and a cylindrical tritium multiplication section. Multiple tritium multiplication sections are evenly arranged in the neutron multiplication section, and the volume ratio of the neutron multiplication section to the tritium multiplication section is in the range of 2:1 to 8:1. The tritium pipes are arranged in an array in the tritium multiplication section.

[0067] Furthermore, the core includes a fuel assembly, and the fuel assembly is divided into multiple sections along the axial direction of the gas-cooled reactor. From the air inlet end to the air outlet end of the fuel assembly, the fissile nuclide enrichment of the fuel assembly increases section by section.

[0068] Furthermore, the fuel assembly is divided into 3-8 sections along the axial direction of the gas-cooled reactor, and the multi-section fuel assembly uses 3-4 types of fuels with different enrichment levels of fissile nuclides.

[0069] Furthermore, the fuel assembly includes a fuel assembly coolant flow channel, and a third gas acceleration device is provided on the fuel assembly coolant flow channel. The third gas acceleration device adopts a structure with a changing cross-sectional area, including a contraction section, or a contraction section, a narrow throat section and an expansion section connected in sequence along the gas flow direction.

[0070] Furthermore, the fuel assembly is cylindrical as a whole and is divided into multiple layers along the radial direction of the gas-cooled stack. The coolant flow channels of the fuel assembly include interlayer flow channels, which are gaps of 2 mm to 20 mm between different layers of fuel assemblies. The fuel assembly is also divided into multiple sectors along the circumferential direction of the gas-cooled stack, so that each layer of fuel assembly has multiple fuel elements. The coolant flow channels of the fuel assembly also include axial channels, and each fuel element has multiple axial channels along the axial direction of the gas-cooled stack.

[0071] Furthermore, the number of axial holes on each fuel element is determined according to the following formula: Where n is the number of axial channels, θ is the central angle of the sector where the fuel element is located, and m is the number of layers where the fuel element is located from the inside to the outside along the radial direction of the gas-cooled reactor.

[0072] Furthermore, the gas-cooled reactor is a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor, and the thermal neutron injection rate of the tritium production module system of the high-flux gas-cooled reactor is 1.0×10 11 ~5.0×10 15 n / cm 2 ·s, and the fast neutron flux rate is 1.5×10 10 ~1.0×10 15 n / cm 2 ·s; the thermal neutron flux rate of the tritium production module system of the high-flux gas-cooled fast reactor is 1.0×10 11 ~5.0×10 15 n / cm 2 ·s, the fast neutron flux rate is 3×10 12 ~5.0×10 15 n / cm 2 ·s.

[0073] Furthermore, the high-flux gas-cooled reactor and high-flux gas-cooled fast reactor use uranium fuel or uranium-thorium MOX fuel, in which the enrichment of U-235 is not less than 15%; if uranium-plutonium MOX fuel, thorium-plutonium MOX fuel or uranium-thorium-plutonium MOX fuel is used, the enrichment of Pu-239 is not less than 10%.

[0074] Furthermore, a coolant flow channel and / or a second neutron multiplying layer and / or a second reflective layer and / or a second moderating layer are arranged between the nuclear fuel sealing isolation layer and the tritium production module system; a coolant flow channel and / or a third neutron multiplying layer and / or a third reflective layer and / or a third moderating layer are arranged between the reactor pressure vessel and the tritium production module system.

[0075] Furthermore, the nuclear fuel sealing isolation layer includes a metal container or a panel, and also includes a fixed support structure. A neutron regulation layer is arranged between the core and the nuclear fuel sealing isolation layer. The neutron regulation layer includes a coolant flow channel, and / or a fourth neutron multiplication layer and / or a fourth reflection layer and / or a fourth moderation layer.

[0076] Furthermore, the thermal neutron flux rate of the tritium production module system of the gas-cooled reactor is 1.0×10 10 ~2.0×10 13 n / cm 2 ·s, and the fast neutron flux rate was 5.0×10 9 ~5.0×10 12 n / cm 2 ·s; if the gas-cooled reactor is a gas-cooled fast reactor, the thermal neutron flux rate of the tritium production module system is 1.0×10 10 ~2.0×10 13 n / cm 2 ·s, and the fast neutron flux rate was 5.0×10 9 ~1.0×10 13 n / cm 2 ·s.

[0077] Furthermore, gas-cooled reactors and gas-cooled fast reactors use uranium fuel or uranium-thorium MOX fuel, in which the enrichment of U-235 is not less than 4.5%; if uranium-plutonium MOX fuel, thorium-plutonium MOX fuel or uranium-thorium-plutonium MOX fuel is used, the enrichment of Pu-239 is not less than 5%.

[0078] By applying the above technical solutions of the present invention, at least the following beneficial effects are achieved:

[0079] 1. In a gas-cooled reactor, by setting up a tritium production module system outside the core to produce tritium, the radiation hazard to reactor components and external personnel and equipment caused by neutron leakage from the gas-cooled reactor core can be resolved, and the thickness of the gas-cooled reactor reflector layer, moderator layer and external shield can be reduced.

[0080] 2. In a gas-cooled reactor, by setting a first gas acceleration device at the reactor coolant inlet, the flow rate of the gas medium in the gas-cooled reactor can be increased, thereby enhancing the gas medium circulation speed and efficiency. By setting up a gas medium physical parameter adjustment system, the pressure and flow rate of the gas medium in the air inlet section of the first gas acceleration device can be adjusted and changed according to different operating conditions of the reactor, such as different operating powers, thereby achieving automatic adjustment of the reactor cooling efficiency and tritium loading efficiency.

[0081] 3. By setting a second gas acceleration device at the coolant inlet of the tritium production module system, the gas-cooled reactor can increase the flow rate of the tritium-containing medium in the tritium production module system, so that the flow rate, pressure and density of the gas medium entering different structural layers of the tritium production module system are different, thereby enhancing the ability and efficiency of the gas medium to carry tritium. At the same time, the ultrasonic wave generated can remove the tritium deposited and attached to the flow channel wall and the tritium production module system, thereby reducing the sedimentation and adsorption loss of tritium.

[0082] 4. The gas-cooled reactor is equipped with a diverter plate to divert the gas coolant entering the core and the gas medium entering the tritium production module system, so that the high-tritium gas medium will not be mixed into the core coolant after entering the tritium production module system, thereby maintaining the tritium radioactivity level of the gas medium in the core coolant system; and the parameters of the gas medium entering different systems are adjusted separately, so that the reactor coolant entering the tritium production module system is coupled with the second gas accelerator, thereby enhancing the ability of the gas medium in the tritium production module system to carry tritium.

[0083] 5. The tritium production module system of the gas-cooled reactor can better realize the functions of neutron multiplication and tritium production by designing the structure of the neutron multiplying layer, the tritium breeding layer or the structure of the tritium breeding multiplication layer. In addition, the position and structure of the tritium pipeline in the tritium production module system can be designed to enhance the transfer capacity and efficiency of tritium in the tritium production module system.

[0084] 6. By designing fuel assemblies in high-flux gas-cooled reactors or high-flux gas-cooled fast reactors to be divided into multiple sections along the axial direction and using fuels with different enrichments of fissile nuclides, the flow rate of the flow channel gas in the core and fuel assemblies is increased through temperature and pressure differences, thereby improving the core cooling efficiency, flattening the axial power distribution of the fuel assemblies, and enhancing core safety.

[0085] 7. In a high-flux gas-cooled reactor (HTR) or a high-flux gas-cooled fast reactor (HTR), the coolant flow path shape of the fuel assembly is designed, and a third gas accelerator is designed in the coolant flow path of the fuel assembly to further increase the coolant gas flow rate and enhance the cooling efficiency of the fuel, thereby achieving tritium production capability under high neutron injection and high temperature conditions.

[0086] To achieve the above-mentioned objectives, a combined system of a gas-cooled reactor and a fusion reactor is proposed, comprising a fusion reactor and a gas-cooled reactor. The fusion reactor includes various fusion reactors using tritium and / or helium-3 as fusion fuel and fusion-fission hybrid reactors. The combined system also includes a tritium supply system, which is connected to the gas-cooled reactor and also to the fusion reactor. The gas-cooled reactor produces tritium, and tritium fuel and / or helium-3 fuel is provided to the fusion reactor through the tritium supply system.

[0087] Furthermore, the tritium supply system includes a tritium collection system, a tritium processing and storage system, and a tritium fuel replenishment system which are connected in sequence. The tritium collection system is connected to the gas-cooled reactor, and the tritium fuel replenishment system is connected to the fusion reactor.

[0088] Furthermore, the tritium processing and storage system includes: a tritium extraction system, a tritium purification and separation system, a tritium storage system and a tritium monitoring system; the tritium monitoring system is associated with the tritium extraction system, the tritium purification and separation system and the tritium storage system, and monitors the equipment and facilities in each system.

[0089] Furthermore, the tritium collection system includes: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion / catalysis system; the tritium fuel replenishment system includes: a fuel pretreatment system and a tritium injection system.

[0090] Furthermore, the input of the tritium collection system is connected to the tritium production module system of the gas-cooled reactor, and the reactor coolant and tritium-containing medium in the tritium production module system enter the tritium supply system.

[0091] Furthermore, the input of the tritium collection system is connected to the core of the gas-cooled reactor, and the reactor coolant in the core enters the tritium supply system. The reactor coolant after separation and purification to remove tritium is returned to the gas-cooled reactor for reuse.

[0092] Furthermore, the combined system also includes a fission fuel bidirectional supply system, including a first nuclear fuel supply system and a second nuclear fuel supply system. The gas-cooled reactor provides one or more of the following substances to the fusion reactor through the first nuclear fuel supply system: depleted uranium, Th-232, U-238 and Pu-239 initial fuel.

[0093] Furthermore, the fusion reactor provides Pu-239 and / or U-233 to the gas-cooled reactor through a second nuclear fuel supply system.

[0094] By applying the above technical solutions of the present invention, at least the following beneficial effects are achieved:

[0095] 1. This combined system, through the installation of a tritium supply system, collects, processes, stores, and transports the tritium produced by the gas-cooled reactor. It can provide tritium fuel and / or helium-3 fuel to fusion reactors or fusion-fission hybrid reactors, thereby solving the problems of tritium self-sustaining and fuel replenishment in fusion reactors and fusion-fission hybrid reactors.

[0096] 2. This combined system sets up a two-way fission fuel supply system, so that the gas-cooled reactor and fusion reactor within the combined system can provide each other with nuclear fuel, achieving the goal of joint symbiosis of gas-cooled reactors and fusion reactors, increasing the utilization rate of fission fuel, reducing total radioactive waste, and enhancing the economy of the combined system.

[0097] 3. This combined system connects the tritium collection system's input to the gas-cooled reactor's tritium production module system and the reactor core. When there is no need to extract or purify the core coolant, only the tritium production module system and the tritium collection system can be connected. The reactor coolant, after separation and purification to remove tritium, can be returned to the gas-cooled reactor for reuse, thereby improving economic efficiency.

[0098] To achieve the above-mentioned objectives, another combined system of a gas-cooled reactor and a fusion reactor is proposed, comprising a gas-cooled reactor and a fusion reactor; a tritium fuel supply system connected to both the gas-cooled reactor and the fusion reactor, wherein the gas-cooled reactor produces tritium and introduces a coolant and a gas medium containing tritium into the tritium fuel supply system to obtain tritium and / or helium-3 fuel, and the tritium fuel and / or helium-3 fuel is transported to the fusion reactor; a fission fuel bidirectional supply system connected to both the gas-cooled reactor and the fusion reactor, wherein the gas-cooled reactor and the fusion reactor supply nuclear fuel to each other through the fission fuel bidirectional supply system; and fusion reactors include various fusion reactors or fusion-fission hybrid reactors using tritium and / or helium-3 as fusion fuel.

[0099] Furthermore, the tritium fuel supply system includes a tritium collection system, a tritium processing and storage system, and a tritium replenishment system which are connected in sequence. The tritium collection system is connected to the gas-cooled reactor, and the tritium replenishment system is connected to the fusion reactor.

[0100] Furthermore, the tritium processing and storage system includes: a tritium extraction subsystem, a tritium purification and separation subsystem, a tritium storage subsystem and a tritium monitoring subsystem; the tritium monitoring subsystem is associated with the tritium extraction subsystem, the tritium purification and separation subsystem and the tritium storage subsystem, and monitors the equipment and facilities of each subsystem.

[0101] Furthermore, the tritium collection system includes: a tritium purification subsystem, a tritium diversion subsystem, a gas cooling and tritium conversion / catalysis subsystem, and the tritium purification subsystem is connected to the gas-cooled reactor.

[0102] Furthermore, the tritium replenishment system includes a fuel pretreatment unit and a tritium injection unit, and the tritium injection unit is connected to the fusion reactor.

[0103] Furthermore, the fission fuel bidirectional supply system includes a first nuclear fuel and isotope reprocessing system connected to both the gas-cooled reactor and the fusion reactor. Through the first nuclear fuel and isotope reprocessing system, the gas-cooled reactor provides one or more of the following substances to the fusion reactor: Th-232, U-238, and Pu-239 initial fuel.

[0104] Furthermore, the fission fuel bidirectional supply system also includes a second nuclear fuel and isotope reprocessing system connected to both the gas-cooled reactor and the fusion reactor. Through the second nuclear fuel and isotope reprocessing system, the fusion reactor provides Pu-239 and / or U-233 to the gas-cooled reactor.

[0105] Furthermore, the first nuclear fuel and isotope reprocessing system includes a spent fuel receiving and dissolution unit, a spent fuel and isotope separation and purification unit, a nuclide extraction unit, and a fusion reactor nuclear fuel manufacturing unit, which are connected in sequence. The spent fuel receiving and dissolution unit is connected to the gas-cooled reactor, and the fusion reactor nuclear fuel manufacturing unit is connected to the fusion reactor.

[0106] Furthermore, the second nuclear fuel and isotope reprocessing system includes a nuclear fuel cladding receiving and disintegration unit, a cladding shearing and decomposition unit, a nuclide separation and purification unit, and a gas-cooled reactor nuclear fuel manufacturing unit, which are connected in sequence. The nuclear fuel cladding receiving and disintegration unit is connected to the fusion reactor, and the gas-cooled reactor nuclear fuel manufacturing unit is connected to the gas-cooled reactor.

[0107] Furthermore, the first nuclear fuel and isotope reprocessing system and the second nuclear fuel and isotope reprocessing system both include a radioactive waste treatment and storage unit and a tritium enrichment unit. The high-tritium waste liquid and waste gas generated by the radioactive waste treatment and storage unit, and the tritium-containing material in the tritium enrichment unit are transported to the tritium collection system and / or the tritium treatment and storage system.

[0108] Furthermore, the gas-cooled reactor includes a tritium production module system and a core. The tritium production module system is arranged on the periphery of the core. The tritium production module system includes tritium breeding material, which reacts with neutrons in the core to produce tritium elements.

[0109] Furthermore, the input end of the tritium purification subsystem is connected to the tritium production module system, or the input end of the tritium purification subsystem is connected to the tritium production module system and the core respectively.

[0110] Furthermore, the tritium purification subsystem includes a dust aerosol filtration unit, a radioactive inert gas filtration unit and an iodine filtration unit connected in sequence. The dust aerosol filtration unit has glass fiber, chemical fiber or aerogel, the radioactive inert gas filtration unit has a nanoporous adsorption material based on carbon, graphite or graphene, and the iodine filtration unit has an iodine adsorber for removing radioactive iodine isotopes in the tritium-laden gas medium.

[0111] Furthermore, the gas cooling and tritium conversion / catalysis subsystem includes a gas medium cooling and tritium catalysis unit, and the tritium diversion subsystem includes a gas-liquid separation and liquid tritium collection unit. The gas medium cooling and tritium catalysis unit has a temperature regulation device and is connected to the output end of the tritium purification subsystem. The output end of the gas medium cooling and tritium catalysis unit is connected to the gas-liquid separation and liquid tritium collection unit to catalytically oxidize the tritium in the gas medium into tritiated water and cool the gas medium. The gas-liquid separation and liquid tritium collection unit has a gas-liquid separator to separate the tritiated water and the gas medium containing gaseous tritium.

[0112] Furthermore, the tritium extraction subsystem includes a tritium physical state conversion unit; and the tritium purification and separation subsystem includes a tritium separation and purification unit.

[0113] Furthermore, the tritium storage subsystem includes a liquid tritium storage unit and a gaseous tritium storage unit.

[0114] Furthermore, the liquid tritium storage unit and the tritium separation and purification unit are both connected to the output end of the gas-liquid separation and liquid tritium collection unit, tritiated water enters the liquid tritium storage unit, and the gaseous medium and gaseous tritium enter the tritium separation and purification unit. The tritium separation and purification unit has a centrifugal purification device to separate and purify the gaseous tritium in the gas medium.

[0115] Furthermore, the tritium separation and purification unit is connected to the gas-cooled reactor, and part of the gas medium in the gas-cooled reactor directly enters the tritium separation and purification unit. After separation and purification to remove tritium, the gas medium enters the coolant system of the gas-cooled reactor for reuse.

[0116] Furthermore, the tritium physical state conversion unit is located between the liquid tritium storage unit and the tritium separation and purification unit. The tritium physical state conversion unit includes an electrolysis device, which ionizes and decomposes the tritiated water in the liquid tritium storage unit to form gaseous tritium, and introduces the gas medium containing gaseous tritium into the tritium separation and purification unit.

[0117] Furthermore, the gas tritium storage unit is connected to the tritium separation and purification unit, and the gas tritium storage unit has a foam palladium or palladium matrix adsorber for adsorbing gaseous tritium for storage.

[0118] Furthermore, the gas tritium storage unit is connected to the fuel pretreatment unit, which has a physical parameter adjustment device to adjust the physical characteristic parameters of gaseous tritium and / or helium-3; the fuel pretreatment unit also includes a device for separating tritium and helium-3, which provides tritium fuel and helium-3 fuel to the fusion reactor respectively after separation.

[0119] Furthermore, the tritium storage subsystem also includes a tritium liquid catalytic conversion unit, a tritium solidification unit, a solid tritium processing and storage unit, a tritium solidified material processing unit, and a tritium debinding unit, which are connected in sequence. The input end of the tritium liquid catalytic conversion unit is connected to the gas tritium storage unit.

[0120] Furthermore, the tritium liquid catalytic conversion unit has an electric heater and a Laval atomizing nozzle, which converts excess gaseous tritium in the gaseous tritium storage unit into liquid tritium and then atomizes it into nano-liquid particles.

[0121] Furthermore, the tritium solidification unit has a molecular reaction bed or a micromolecular reaction bed, which catalytically solidifies the nano liquid particles and the micro-nano magnesium particles to form tritiated magnesium powder particles. The tritiated magnesium powder particles are processed into blocks and stored in the solid tritium processing and storage unit.

[0122] Furthermore, the tritium solidification product processing unit has a crushing device to process the blocky magnesium tritide into magnesium tritide powder particles, the tritium debinding unit has a hydrolysis device to hydrolyze the magnesium tritide powder particles, and the output end of the tritium debinding unit is connected to the tritium physical state conversion unit.

[0123] The application of the technical solution of the present invention achieves at least the following beneficial effects:

[0124] 1. The combined system of the present application provides a tritium supply system and designs the specific composition and structure of the tritium supply system. The tritium produced by the gas-cooled reactor is collected, processed, stored and transported in the tritium supply system to obtain tritium fuel and / or helium-3 fuel, which is then provided to the fusion reactor to solve the problems of tritium self-sustaining and fuel replenishment in the fusion reactor.

[0125] 2. The combined system of the present application sets up a two-way fission fuel supply system, so that the gas-cooled reactor and fusion reactor within the combined system can provide nuclear fuel to each other, achieving the goal of joint symbiosis of gas-cooled reactor and fusion reactor, increasing the utilization rate of fission fuel, reducing the total radioactive waste, enhancing the economy of the combined system, and improving environmental friendliness.

[0126] 3. The combined system of the present application can convert the excess gaseous tritium stored in the gas tritium storage unit into solid blocks, so as to store the excess tritium produced by the gas-cooled reactor in a solid state, and then convert it into tritium fuel and / or helium-3 fuel for use when needed, thereby improving storage efficiency, facilitating long-term storage and transportation, and solving the problem of excess tritium produced by the gas-cooled reactor.

[0127] 4. The combined system of the present application is connected to the tritium production module system and the core of the gas-cooled reactor by setting the input of the tritium collection system. When there is no need to extract or purify the core coolant for tritium, only the connection between the tritium production module system and the tritium collection system can be opened, and the reactor coolant after separation and purification to remove tritium can be returned to the gas-cooled reactor for reuse, thereby improving economic efficiency. BRIEF DESCRIPTION OF THE DRAWINGS

[0128] The accompanying drawings, which constitute part of the present invention, are intended to provide a further understanding of the present invention. The exemplary embodiments of the present invention and their descriptions are intended to explain the present invention and do not constitute an undue limitation of the present invention. In the accompanying drawings:

[0129] FIG1 shows a partial cross-sectional view of the tritium production module system in Example 1;

[0130] FIG2 shows a schematic diagram of the flow direction of tritium-containing media in the tritium production module system in Example 1;

[0131] FIG3 shows a schematic cross-sectional view of the reactor in Example 1;

[0132] FIG4 shows a schematic cross-sectional view of the reactor in Example 2;

[0133] FIG5 shows a schematic diagram of the tritium system in Example 3;

[0134] FIG6 shows a schematic longitudinal cross-sectional view of the main structure of a gas-cooled reactor according to Example 4;

[0135] FIG7 shows a schematic cross-sectional view of a gas-cooled reactor according to Example 4;

[0136] FIG8 shows a schematic cross-sectional view of the specific structure of a gas-cooled reactor according to Example 6;

[0137] FIG9 shows a schematic diagram of the combined system of Example 7;

[0138] FIG10 shows a schematic diagram of a tritium fuel supply system according to Example 8;

[0139] FIG11 shows a schematic diagram of the fission fuel bidirectional supply system of Example 8. DETAILED DESCRIPTION

[0140] It should be noted that, in the absence of conflict, the embodiments and features of the embodiments of the present invention can be combined with each other. The present invention will be described in detail below with reference to the accompanying drawings and in combination with the embodiments.

[0141] The present invention is described in further detail below with reference to specific embodiments. These embodiments are not to be construed as limiting the scope of protection claimed by the present invention. The term "including" when used indicates the presence of a feature, but does not exclude the presence or addition of one or more other features; the terms "lateral", "upper", "lower", "front", "back", "left", "right", "top", "bottom", "inside", "outside" and the like indicate directions or positional relationships based on the directions or positional relationships shown in the accompanying drawings, and are only for ease of description, and do not indicate or imply that the device or element referred to must have a specific direction, be constructed and operated in a specific direction, and therefore cannot be construed as limiting the present invention; in addition, the terms "first" and "second" are only used for descriptive purposes, and cannot be construed as indicating or implying relative importance.

[0142] Throughout this description, it should be noted that, unless otherwise specified or limited, the terms "mounted," "connected," and "connected" should be interpreted broadly. For example, they can refer to fixed connections, removable connections, or integral connections; they can refer to direct connections or indirect connections through an intermediary; and they can refer to internal communication between two components. Those skilled in the art will understand the specific meanings of these terms in the present invention. Furthermore, throughout this description, unless otherwise specified, "plurality" means two or more.

[0143] Example 1:

[0144] This embodiment proposes a tritium-producing module system within a reactor, as shown in Figure 1. The tritium-producing module system has a multi-layer structure distributed radially along the reactor. The tritium-producing module system includes a tritium-producing area and a circulation area. The tritium-producing area includes tritium breeding materials. The tritium breeding materials react with neutrons to produce tritium elements. Through the circulation area, the tritium-producing module system is connected to the external fluid of the tritium-producing module system.

[0145] Specifically, the circulation area includes a tritium conduit 101, which circulates reactor coolant and tritium-containing media, primarily for conducting tritium produced in the tritium-producing area out of the tritium-producing module system. The tritium conduit 101 extends axially along the reactor. Multiple holes 102 are defined in its wall, providing fluid communication between the tritium conduit 101 and the tritium-producing area.

[0146] The tritium pipe 101 is a single-layer or multi-layer pipe. Preferably, the tritium pipe 101 is a multi-layer pipe, with multiple holes 102 formed in the pipe wall of any one layer or any multiple layers of the multi-layer pipe. Further preferably, as shown in FIG1 , the tritium pipe 101 is a two- to three-layer pipe, with holes 102 formed in the pipe wall of each layer. The number of holes 102 increases layer by layer, or the size of holes 102 increases layer by layer, from the outer layer to the inner layer of the tritium pipe 101. This results in a decrease in pressure and an increase in airflow rate layer by layer from the outer layer to the inner layer of the tritium pipe, thereby further enhancing the efficiency of tritium release and diffusion from the tritium-producing region into the tritium pipe.

[0147] Preferably, the holes 102 can be arranged at regular intervals along the extension direction of the tritium pipeline. The holes can be shaped in various shapes, such as circular or square. Furthermore, along the extension direction of the tritium pipeline 101, the holes 102 on any two adjacent layers of the pipeline wall can be positioned identically or staggered. By configuring the tritium pipeline as a multi-layer system with holes in the pipeline wall, and by adjusting the size, quantity, and location of the holes, this modular tritium production system facilitates the release and diffusion of tritium from the modular system into the tritium pipeline.

[0148] In the present application, as shown in Figures 1 and 2, the tritium production module system includes a coolant inlet, which includes a fluid acceleration device 103, and the coolant inlet is connected to the tritium pipeline 101. Preferably, the fluid acceleration device 103 is connected to the tritium pipeline 101. Through the connection and coordination between the tritium pipeline 101 and the fluid acceleration device 103, the flow rate, pressure, and density of the gas medium entering different structural layers of the tritium production module system are different, thereby enhancing the ability and efficiency of the gas medium in the tritium pipeline 101 to carry tritium.

[0149] Specifically, the fluid acceleration device 103 is a structure with a variable cross-sectional area, and is not limited to a tubular structure with a variable cross-sectional area, or a plate-like structure. The fluid acceleration device 103 includes a contraction section, a narrow throat section, and an expansion section sequentially connected along the flow direction. The cross-sectional area of ​​the contraction section changes from large to small along the flow direction, and the cross-sectional area of ​​the expansion section changes from small to large along the flow direction. Preferably, the fluid acceleration device 103 is a Laval nozzle or a structure similar to a Laval nozzle designed using the Bernoulli principle and related physical principles, which can accelerate the gas, and under certain conditions, can even accelerate it to supersonic speed. In addition, in other embodiments, the fluid acceleration device 103 can include only a contraction section, which can also play a role in accelerating the gas.

[0150] For details, please refer to the direction of air flow in the tritium production module system shown in Figure 2. By setting a fluid acceleration device at the coolant inlet, the tritium production module system can increase the flow rate of the tritium medium in the tritium production module system, so that the flow rate, pressure and density of the gas medium entering different structural layers of the tritium production module system are different, thereby enhancing the ability and efficiency of the gas medium to carry tritium. The ultrasonic vibrations generated at the same time can remove tritium deposited and attached to the wall of the flow channel and the tritium production module system, thereby reducing the sedimentation loss of tritium. In addition, by connecting the fluid acceleration device with the tritium pipeline, and designing the number and size of holes on the wall of each layer of the tritium pipeline, the air flow rate of the tritium pipeline increases layer by layer from the outside to the inner layer, and the pressure decreases layer by layer, thereby further enhancing the efficiency of tritium release and diffusion from the tritium production area to the tritium pipeline.

[0151] Examples 1 and 2 of the present application both take a gas-cooled reactor as an example to illustrate the structural shape and other contents of the tritium production module system arranged inside the gas-cooled reactor. These two embodiments are only preferred. In some other embodiments, the tritium production module system may also be used in pressurized water reactors, heavy water reactors, fast neutron reactors and other reactor types.

[0152] Compared to other reactor types, gas-cooled reactors offer three major physical advantages for tritium production. First, gas-cooled reactors have a high core neutron leakage rate. By placing a tritium production module system around the gas-cooled reactor core, neutrons leaking from the core react with tritium breeder material in the production module system to produce tritium. The high neutron reaction cross section of the material reduces neutron irradiation damage to key equipment such as the pressure vessel and the radiation level outside the reactor. The value-added graphite reflector layer is replaced with a valuable tritium production module system, and the thickness of the gas-cooled reactor reflector layer, moderator layer, and external shielding can be reduced. Second, the high temperature within the gas-cooled reactor, generally exceeding 400-800°C, facilitates the release and diffusion of tritium from the production module system, creating excellent conditions for online tritium extraction. Third, the gas coolant in a gas-cooled reactor has excellent tritium carrying capacity. Its physical and chemical properties are stable (such as He) and differ significantly from those of tritium (such as carbon dioxide), making it easy to separate and purify tritium.

[0153] Using gas-cooled reactors to produce tritium can solve the radiation hazards of neutron leakage from the high core of gas-cooled reactors to reactor components and external personnel and equipment, and can also reduce the thickness of the gas-cooled reactor's reflector layer, moderator layer and external shielding body.

[0154] As shown in Figure 3, in this embodiment, the gas-cooled reactor includes a core 1014, a first neutron regulation layer 1015, a nuclear fuel containment barrier 1016, and a reactor pressure vessel 1017, arranged radially from the inside out. The tritium production module system is located between the nuclear fuel containment barrier 1016 and the reactor pressure vessel 1017. The first neutron regulation layer 1015 can be configured as a coolant channel, a neutron multiplication layer, a reflector layer, and / or a moderator layer. The nuclear fuel containment barrier 1016 comprises a metal container or enclosure, as well as fixed support members.

[0155] The gas-cooled reactor includes a neutron conditioning layer that adjusts the energy and quantity of neutrons, thereby improving the tritium production efficiency of the tritium production module system. The neutron conditioning layer includes a first neutron conditioning layer 1015, a second neutron conditioning layer, and a third neutron conditioning layer. Coolant flow channels, neutron multiplication layers, reflective layers, and / or moderator layers can be installed in each neutron conditioning layer as required.

[0156] In a gas-cooled reactor, a second neutron regulation layer can be provided between the nuclear fuel containment isolation layer 1016 and the tritium production module system, and / or a third neutron regulation layer can be provided between the reactor pressure vessel 1017 and the tritium production module system. The gas-cooled reactor proposed in this application improves the utilization of core neutrons and tritium production efficiency by providing neutron regulation layers on both sides of the tritium production module system and between the core and the nuclear fuel containment isolation layer. By varying the structure of the neutron regulation layers, the gas-cooled reactor can be adapted to different types and states of gas-cooled reactors.

[0157] Specifically, the tritium production module system includes a cladding 104 and a tritium production layer group. The cladding 104 is arranged at intervals along the radial direction of the reactor. That is, the cladding 104 is located at the outermost layer of the tritium production module system along the radial direction of the reactor, and the tritium production layer group is located between two layers of cladding 104.

[0158] The tritium-producing layer group includes at least one of a tritium breeding layer 106 and a tritium breeding multiplication layer 107 , wherein the tritium breeding layer 106 and the tritium breeding multiplication layer 107 both include a tritium-producing region, and the tritium-producing region includes tritium breeding materials.

[0159] A neutron multiplying layer 105 can also be provided within the tritium-producing layer group. Neutron multiplying layer 105 comprises neutron multiplying material. Neutron multiplying layer 105 can be provided together with either or both of tritium breeder layer 106 and tritium multiplier layer 107. Preferably, when only tritium breeder layer 106 is provided within the tritium-producing layer group, neutron multiplying layer 105 is also provided. Tritium conduit 101 is located within the tritium-producing layer group.

[0160] The reactor coolant is a gas, and the cooling gas includes an inert gas such as helium (He), or a gas with stable physical and chemical properties such as carbon dioxide (CO2). Preferably, the reactor coolant gas is an inert gas such as helium (He).

[0161] Fuel element shapes include: spherical, cylindrical, plate-like, block-like, cross-plate-like, curved plate-like, and hollow cylindrical. The cross-sectional shapes of cylindrical fuel elements include: circular, regular polygonal (such as square, regular hexagon, regular octagon, etc.). The inner and outer cross-sectional shapes of hollow cylindrical fuel elements include: circular, regular polygonal (such as square, regular hexagon, regular octagon, etc.), and the inner and outer shapes can be the same or different.

[0162] Preferably, as shown in FIG3 , the reactor type used in the project is a gas-cooled reactor with a hexagonal core. Generally, a neutron multiplication layer is provided in the first neutron regulation layer 1015 of the gas-cooled reactor, so that the thermal neutron injection rate of the tritium production module system of the gas-cooled reactor is 1.0×10 10 ~2.0×10 13 n / cm 2 ·s, and the fast neutron flux rate was 5.0×10 9 ~5.0×10 12 n / cm 2 ·s.

[0163] In a gas-cooled fast reactor, a moderator layer can be set in the first neutron regulation layer 1015, and the thermal neutron injection rate of the tritium production module system is 1.0×10 10 ~2.0×10 13 n / cm 2 ·s, and the fast neutron flux rate was 5.0×10 9 ~1.0×10 13 n / cm 2 ·s.

[0164] To further increase the neutron fluence (rate) at the tritium production module system, the gas-cooled reactor can be improved to a high-flux gas-cooled reactor. In the high-flux gas-cooled reactor, a coolant flow channel is provided in the first neutron regulation layer 1015 to enhance the cooling efficiency, so that the thermal neutron fluence rate of the tritium production module system is 1.0×10 11 ~5.0×10 15 n / cm 2 ·s, and the fast neutron flux rate is 1.5×10 10 ~1.0×10 15 n / cm 2 ·s, thereby increasing the generation capacity and efficiency of tritium.

[0165] The gas-cooled reactor can also be improved into a high-flux gas-cooled fast reactor. In the high-flux gas-cooled fast reactor, a coolant flow channel is provided in the first neutron regulation layer 1015, and a moderator layer or a reflector layer is provided. The thermal neutron flux rate of the tritium production module system is 1.0×10 11 ~5.0×10 15 n / cm 2 ·s, the fast neutron flux rate is 3×10 12 ~5.0×10 15 n / cm 2 ·s.

[0166] The core fuel is a material containing uranium, thorium, and plutonium, including AO2, AC, AN, or MOX ceramic fuel, or coated TRISO fuel. A is one of uranium, thorium, and plutonium, and MOX includes any two or three of these. Preferably, the gas-cooled reactor core uses uranium fuel with a minimum U-235 enrichment of no less than 4.5%, a maximum enrichment of 20%, and an average enrichment of no less than 8% to ensure the neutron flux (quantity) of the tritium production module system and the tritium production capacity.

[0167] In order to increase the neutron injection of the reactor, MOX fuel is used in the project. The U-235 enrichment in the fuel is 0.3%, the minimum enrichment of Pu-239 in the fuel is not less than 5%, the maximum enrichment is 60%, and the average enrichment is 8% to 25%.

[0168] For high-flux gas-cooled reactors (HFRs) and high-flux gas-cooled fast reactors (HFRs), if uranium fuel or uranium-thorium MOX fuel is used, the U-235 enrichment in the fuel must be no less than 15%. If uranium-plutonium MOX fuel, thorium-plutonium MOX fuel, or uranium-thorium-plutonium MOX fuel is used, the Pu-239 enrichment in the fuel must be no less than 10%.

[0169] As shown in Figures 1-3, in this embodiment, the tritium-producing layer group includes a neutron multiplying layer 105 and a tritium breeder layer 106 arranged radially along the reactor. The tritium breeder layer 106 is located outside the neutron multiplying layer 105, and at least a portion of the tritium conduit 101 is located within the tritium breeder layer 106. The neutron multiplying layer 105 is used to multiply neutrons, and the tritium breeder layer 106 is used to allow neutrons to interact with tritium breeder material to produce tritium.

[0170] The tritium production module system also includes a partition 109, which is positioned between different types of layers in the tritium production layer group, specifically, between the neutron multiplying layer 105 and the tritium breeder layer 106. In other embodiments, the tritium production layer group includes a first circulation structure in which the neutron multiplying layer 105 and the tritium breeder layer 106, arranged radially along the reactor, circulate multiple times, with partitions 109 positioned between different layers of the tritium production layer group. This circulation structure can enhance the tritium production module system's neutron utilization efficiency.

[0171] The tritium production module system also includes a tritium-proof layer, adjacent to the cladding 104, and employing a coating or low-permeability structure. The tritium-proof layer comprises an oxide and a titanium-containing ceramic. The oxide comprises one or more of the following: Cr2O3, Al2O3, and Ti2O2. The titanium-containing ceramic is preferably titanium aluminum carbide. The tritium-proof layer effectively prevents tritium from penetrating outside the tritium production module system and causing loss.

[0172] The cladding material includes, but is not limited to, one or more of the following: austenitic stainless steel, martensitic stainless steel, ferritic steel, vanadium alloy, zirconium alloy, copper alloy, titanium alloy. Preferably, the cladding thickness is 5 mm to 30 mm.

[0173] The tritium production module system also includes a reflector or moderator layer 1010. The materials for this layer include, but are not limited to, one or more of the following: graphite, isostatically pressed graphite, nuclear-grade graphite, boron carbide, silicon carbide, boron-containing silicon carbide, beryllium oxide, or a beryllium-containing compound. The reflector layer reflects neutrons, improving neutron utilization and increasing tritium production.

[0174] The tritium production module system also includes an irradiation product production layer 1011, which is used to produce irradiated products. Materials used in this layer include, but are not limited to, one or more of the following: Np-237 and its compounds for producing Pu-238, and Co-59 and its compounds for producing Co-60. As shown in Figure 2, partitions 109 are placed on both sides of this layer.

[0175] In some other embodiments, the irradiated product production layer 1011 may also be placed between any two layers of the neutron multiplication layer, tritium breeding layer, tritium breeding multiplication layer, moderator 1010 or reflection layer, and a partition 109 is provided between the irradiated product production layer and other layers.

[0176] To sum up, preferably, in this embodiment, the tritium production module system includes a cladding 104, a tritium penetration prevention layer, a neutron multiplication layer 105, a partition 109, a tritium breeding layer 106, a partition 109, an irradiated product production layer 1011, a partition 109, a reflection layer or a moderation layer 1010, a tritium penetration prevention layer, and a cladding 104, which are arranged in sequence from the inside to the outside along the radial direction of the reactor.

[0177] The tritium production module system also includes a coolant channel, which has a similar function to the tritium pipe 101 and is used for the circulation of reactor coolant and / or tritium-containing medium. The coolant channel is arranged in the gaps between the layers of the tritium production module system, and / or inside the cladding 104 and / or the partition 109.

[0178] Preferably, the thickness of the cladding and / or the partition is greater than 1 mm. If a coolant channel is provided in the cladding and / or the partition, the thickness of the cladding and / or the partition with the coolant channel is greater than 3 mm.

[0179] The tritium production module system can be completely or partially surrounded by the periphery of the core 1014 in the circumferential direction. The periphery of the core 1014 can include multiple tritium production module systems with the same or different structures. The multiple tritium production module systems can be evenly or unevenly arranged in a 360° angle range, or evenly or unevenly arranged at certain angles in a partial angle range of the periphery of the core.

[0180] The shape of the tritium production module system includes one or more of the following shapes: 360° overall hollow circular cylinder, hollow arc cylinder within an angle of 1° to 359°, cylinder, polygonal prism, trapezoidal cross-section cylinder, fan-shaped cross-section cylinder, and cube.

[0181] In the present application, the thickness of the tritium production module system along the radial direction of the reactor is 1 cm to 100 cm. Preferably, the thickness of the tritium production module system is 15 cm to 60 cm.

[0182] Preferably, as shown in Figure 3, the tritium production module system is shaped like a circular cylinder, completely surrounding the reactor core in the circumferential direction. The tritium production module system is composed of multiple tritium production submodules spliced ​​together circumferentially, with the number of tritium production submodules ranging from 4 to 24. Specifically, the tritium production submodules are shaped like a cylinder with a sector cross-section angled between 15° and 90°.

[0183] Further preferably, as shown in Figure 3, partitions 109 are provided between adjacent tritium-producing submodules to prevent direct contact between materials in adjacent tritium-producing submodules. Tritium conduits 101 circumferentially surround the core in the tritium breeder layer 6, with 2-6 tritium conduits provided in each tritium-producing submodule.

[0184] This tritium production module system is completely surrounded by the reactor in the circumferential direction and is composed of a certain number of tritium-producing daughter modules, so that the reactor can achieve the maximum tritium production effect. When problems occur in some tritium-producing daughter modules, they can be easily replaced, thereby ensuring the stability of the reactor's tritium production.

[0185] Preferably, both the neutron multiplying layer 105 and the tritium breeder layer 106 employ a structure comprising material balls filled in a pebble bed. The neutron multiplying layer 105 comprises neutron multiplying material balls containing a neutron multiplying material, which includes beryllium and beryllium-containing compounds, such as beryllium, BeO, or beryllium-containing ceramics. The tritium breeder layer 106 comprises tritium breeder material balls containing a tritium breeding material, which includes one or a mixture of the following: Li2O, Li2TiO3, LiAlO2, Li4SiO4, and Li2ZrO3 ceramics.

[0186] The diameter of the neutron multiplication material balls and tritium breeding material balls is 0.1mm-10mm, and the filling rate is 40%-80%. Preferably, the diameter is 0.2mm-2mm, and the filling rate is 50%-70%, to achieve better neutron multiplication and tritium breeding effects.

[0187] In this application, the enrichment of Li-6 in the tritium breeder material is 7.5% to 90%, and the enrichment of Li-7 is 10% to 92.5%, with the total enrichment of Li-6 and Li-7 being 100%. Tritium breeder material with a Li-7 enrichment of 50% to 92.5% is positioned close to the reactor core, while tritium breeder material with a Li-6 enrichment of 50% to 90% is positioned away from the core.

[0188] Fast neutrons with energies greater than 1.0 MeV, which have a higher proportion in the hard neutron energy spectrum near the core, react with Li-7 to produce tritium (Li-7 has a large cross-section for fast neutrons with an energy of 2.47 MeV). By slowing down the neutrons through the previous material layer, the neutron energy spectrum is "softened" to increase the proportion of low-energy and thermal neutrons, thereby increasing the tritium production rate with Li-6, ultimately reducing the manufacturing cost of tritium breeder materials and improving the tritium production rate.

[0189] In other embodiments, a tritium multiplication layer can be added to the tritium-producing layer group. The tritium multiplication layer also adopts the structure of material balls filled in the ball bed. The tritium multiplication layer includes neutron multiplication material balls and tritium multiplication material balls; or the tritium multiplication layer includes tritium multiplication material balls, the core part of the tritium multiplication material ball has tritium multiplication material, and the shell part of the tritium multiplication material ball has neutron multiplication material.

[0190] The tritium-producing layer group can be designed as a second circulation structure, in which any arrangement and combination of the neutron multiplying layer, tritium breeding layer and tritium breeding multiplication layer arranged along the radial direction of the reactor is circulated once or multiple times.

[0191] As shown in FIG2 , preferably, a tritium-producing layer group gas inlet can be provided at the tritium-producing layer group, i.e., the neutron multiplication layer and the tritium breeding layer. The tritium-producing layer group gas inlet is provided with a support structure and a first filter 108 to allow the gas medium to enter and prevent the material in the tritium-producing layer group from leaking out.

[0192] In addition, a second filter screen or filter membrane is provided inside or outside the wall of the tritium pipeline 101 to prevent or reduce the entry of materials or dust in the tritium production layer group into the tritium pipeline, and also to prevent graphite dust and other impurities in the core from entering the tritium production module system.

[0193] The first filter 108 or the second filter may be made of glass fiber, chemical fiber, nano aerogel and the like, preferably graphene aerogel.

[0194] Example 2:

[0195] Compared with Example 1, the position, shape, and arrangement of the tritium production module system in the gas-cooled reactor, including the tritium pipeline, fluid acceleration device 103, and filter screen, are substantially the same in Example 2. The difference is that, as shown in FIG4 , the tritium production module system in Example 2 consists of a cladding 104 and a tritium multiplication layer 107 between the claddings. A tritium permeation prevention layer may also be provided adjacent to the cladding 104.

[0196] In this embodiment, the tritium-producing layer group preferably does not include the tritium breeding layer 106 and the neutron multiplying layer 105. The tritium breeding multiplying layer 107 in this embodiment includes a neutron multiplying section 1012 and a cylindrical tritium breeding section 1013. Multiple tritium breeding sections 1013 are evenly arranged within the neutron multiplying section 1012, ensuring that the neutron flux within each tritium breeding section 1013 is at the same order of magnitude. Preferably, a partition 109 is provided around the cylindrical tritium breeding section 1013 to separate the materials of the neutron multiplying section 1012 from those of the tritium breeding section 1013. In the tritium breeding multiplying layer 107, the volume ratio of the neutron multiplying section 1012 to the tritium breeding section 1013 is within a range of 2:1 to 8:1. The tritium pipes 101 are arranged in an array within the tritium breeding section 1013.

[0197] Preferably, the number of tritium breeding sections 1013 in each tritium-producing submodule does not exceed six, and as shown in FIG4 , there are three. This ensures that the distance difference between the material at all locations within the tritium breeding section 1013 and the nearest tritium pipe 101 does not exceed 50% of the diameter of the tritium breeding section 1013, thereby facilitating the release and diffusion of tritium in the tritium breeding section 1013.

[0198] In some other embodiments, the tritium-producing layer group includes a second circulation structure, in which any combination of the neutron multiplying layer 105, tritium breeder layer 106, and tritium multiplication layer 107 arranged radially along the reactor undergoes multiple cycles. Separators 109 may be provided between the different layers. The shapes and structures of the neutron multiplying layer 105 and tritium breeder layer 106 are similar to those described in Example 1. This circulation structure achieves high neutron utilization within the reactor.

[0199] It should be noted that the structure of the tritium multiplication layer 107 described in this embodiment is only preferred and is not limited to the structure described in Figure 4. For example, the cross-sectional shape of the tritium multiplication portion 1013 can be other shapes, or the tritium multiplication layer 107 can only include tritium multiplication material balls.

[0200] In some other embodiments, the tritium-producing layer group may be configured as a combination of a tritium breeding multiplication layer 107 and a neutron multiplication layer 105 .

[0201] Specifically, the tritium multiplication layer 107 can be configured as a mixture of neutron multiplication material balls and tritium multiplication material balls. The tritium multiplication layer 107 can also include tritium multiplication material balls, the core of the tritium multiplication material balls has tritium multiplication material, and the shell of the tritium multiplication material balls has neutron multiplication material.

[0202] If the tritium multiplication layer 107 is a mixture of neutron multiplication material spheres and tritium multiplication material spheres, such as the structure of the tritium multiplication layer 107 described in this embodiment, the ratio of neutron multiplication material spheres to tritium multiplication material spheres is 2:1 to 8:1. The diameter of the neutron multiplication material spheres, tritium multiplication material spheres, or tritium multiplication material spheres is 0.1 mm to 10 mm, and the filling rate is 40% to 80%. Preferably, the diameter is 0.2 mm to 2 mm, and the filling rate is 50% to 70%. This achieves better neutron multiplication and tritium multiplication effects.

[0203] In this embodiment, preferably, the irradiated product production layer 1011 is not provided. Furthermore, by utilizing the neutron multiplication unit 1012 as a neutron reflector, the tritium production module system does not require a reflector layer or a moderator layer 1010. This greatly simplifies the structure of the tritium production module system.

[0204] In addition, in order to take isotope production into consideration, no more than one-half of the total amount of materials in the tritium breeding section 1013 can be filled with isotope production materials.

[0205] In some other embodiments, an irradiation product production layer 1011 or a reflection layer or a moderation layer 1010 may also be provided in the tritium production module system described in this embodiment.

[0206] In summary, from the above description, it can be seen that Embodiment 1 and Embodiment 2 of the present invention achieve the following technical effects:

[0207] 1. By installing a fluid acceleration device at the coolant inlet, this tritium production module system can increase the flow rate of the tritium-containing medium within the tritium production module system, resulting in different flow rates, pressures, and densities of the gas medium entering different structural layers of the tritium production module system, thereby enhancing the gas medium's ability and efficiency to carry tritium. Simultaneously, the generated ultrasonic vibrations can remove tritium deposited and attached to the flow channel walls and within the tritium production module system, thereby reducing tritium sedimentation losses. 2. By configuring the tritium pipelines as multiple layers with holes in the pipeline walls, and by adjusting the number of holes, this tritium production module system facilitates the release and diffusion of tritium from the tritium production module system into the tritium pipelines. Furthermore, by connecting the tritium pipelines to the fluid acceleration device, the airflow rate increases and the pressure decreases layer by layer from the outer layer to the inner layer of the tritium pipeline, further enhancing the efficiency of tritium release and diffusion from the tritium production area to the tritium pipeline. 3. This tritium production module system, by providing a neutron multiplication layer, a tritium breeding layer, or a tritium breeding multiplication layer structure, enables the system to effectively achieve neutron multiplication and tritium production. By allocating Li-6 and Li-7 to locations with varying abundances, the tritium production rate is increased. Utilizing a gas-cooled reactor for tritium production mitigates the radiation hazards posed by neutron leakage from the gas-cooled reactor's high core to reactor components, external personnel, and equipment, and reduces the thickness of the gas-cooled reactor's reflector layer, moderator layer, and external shielding. 4. This tritium production module system, by providing a support structure and a first filter at the tritium production layer group's air inlet, allows gaseous media to enter and prevents leakage of materials from the tritium production module system. A second filter or membrane is provided on the inside or outside of the tritium pipeline wall to prevent or reduce the ingress of materials or dust from the tritium production layer group into the tritium pipeline, and also prevents graphite dust and other impurities from the reactor core from entering the tritium production module system. 5. The tritium production module system is completely surrounded by the reactor in the circumferential direction and is composed of a certain number of tritium-producing daughter modules. This allows the reactor to achieve the maximum tritium production effect. When a part of the tritium-producing daughter modules has problems, they can be easily replaced, thereby ensuring the stability of the reactor's tritium production. 6. The gas-cooled reactor proposed in this application can solve the radiation hazards of high-core neutron leakage in the gas-cooled reactor to reactor components and external personnel and equipment by setting a tritium production module system around the core to produce tritium elements, and can also reduce the thickness of the gas-cooled reactor's reflective layer, moderation layer, and external shielding. 7. The gas-cooled reactor proposed in this application can improve the utilization rate of core neutrons in the gas-cooled reactor and improve tritium production efficiency by setting neutron regulation layers on both sides of the tritium production module system and between the core and the nuclear fuel sealing isolation layer. By changing the structure of the neutron regulation layer, it can adapt to gas-cooled reactors of different types and different states.

[0208] Example 3:

[0209] Based on Examples 1 and 2, the present application further proposes a tritium system, as shown in FIG5 , which includes any one of the tritium production module systems proposed in Examples 1 and 2. The tritium system also includes a tritium fuel supply system 1018 , which is connected to the tritium production module system. The reactor coolant and tritium-containing medium in the tritium production module system are input into the tritium fuel supply system 1018 to obtain tritium and / or helium-3 fuel, which is then delivered to the fusion reactor 1026 .

[0210] It should be noted that, in the present application, the fusion reactor 1026 here includes all fusion reactors and fusion-fission hybrid reactors that use tritium and / or helium-3 (He-3) as fusion fuel.

[0211] Specifically, the tritium fuel supply system 1018 includes a tritium collection system 1019, a tritium processing and storage system 1020, and a tritium replenishment system 1021, which are connected in sequence. The tritium collection system 1019 is connected to the tritium production module system, and the tritium replenishment system 1021 is connected to the fusion reactor 1026.

[0212] Furthermore, the tritium processing and storage system 1020 includes: a tritium extraction system 1022, a tritium purification and separation system 1023, a tritium storage system 1024 and a tritium monitoring system. The tritium monitoring system is respectively associated with the tritium extraction system 1022, the tritium purification and separation system 1023, and the tritium storage system 1024 to monitor the key equipment and facilities of each system.

[0213] The "association" here means that there is a physical connection, wireless communication connection or data transmission connection between the equipment in the tritium monitoring system and the equipment to be monitored in each subsystem of the tritium treatment storage system 1020, so as to realize different monitoring functions.

[0214] Preferably, the coolant and tritium-containing medium in the tritium pipeline in the tritium production module system are processed by some auxiliary equipment and facilities in the tritium production module system and transported to the tritium fuel supply system 1018. After being processed by the tritium collection system 1019 or the tritium purification and separation system 1023, the reactor coolant can be returned to the gas-cooled reactor for reuse, thereby improving economic efficiency.

[0215] The tritium collection system 1019 includes a tritium purification system, a tritium diversion system, a gas cooling system, and a tritium conversion / catalysis system. The tritium replenishment system 1021 includes a fuel pretreatment system and a tritium injection system. The tritium injection system injects tritium and / or helium-3 fuel into the fusion reactor 1026.

[0216] In summary, from the above description, it can be seen that the above-mentioned embodiment 3 of the present invention achieves the following technical effects:

[0217] The tritium system proposed in this application sets up a tritium fuel supply system connected to the tritium production module system, collects, processes, stores and transports the tritium produced in the tritium production module system through the tritium fuel supply system, and can deliver tritium and / or helium-3 fuel to the fusion reactor, thereby solving the problem of tritium self-sustaining of the fusion reactor and laying the foundation for the establishment of a symbiotic / combined system between gas-cooled reactors and fusion reactors.

[0218] Example 4:

[0219] This embodiment provides a gas-cooled reactor, as shown in FIG7 , comprising a core 1014, a nuclear fuel containment barrier 1016, and a reactor pressure vessel 1017, arranged radially from the inside to the outside of the gas-cooled reactor. The reactor also comprises a tritium production module system 204, which is located peripherally of the core 1014 and between the nuclear fuel containment barrier 1016 and the reactor pressure vessel 1017. The tritium production module system 204 includes tritium breeding material, which reacts with neutrons generated by the core 1014 to produce tritium. The nuclear fuel containment barrier 1016 comprises a metal container or enclosure, and also includes fixed support members.

[0220] In a gas-cooled reactor, by arranging a tritium production module system 204 outside the core to produce tritium, the radiation hazard to reactor components and external personnel and equipment caused by neutron leakage from the gas-cooled reactor core can be resolved, and the thickness of the gas-cooled reactor's reflector layer, moderator layer and external shielding body can be reduced.

[0221] As shown in FIG6 , the gas-cooled reactor includes a reactor coolant inlet, at which a first gas acceleration device 206 is provided, and a gas medium physical parameter adjustment system 2061 is provided on the first gas acceleration device 206 .

[0222] The first gas acceleration device 206 has a structure with a variable cross-sectional area, and is not limited to a tubular structure or a plate-like structure with a variable cross-sectional area. It includes a contraction section, a narrow throat section, and an expansion section connected in sequence along the direction of gas flow. The cross-sectional area of ​​the contraction section decreases along the flow direction, and the cross-sectional area of ​​the expansion section increases along the flow direction. Preferably, the first gas acceleration device 206 has a Laval nozzle designed using the Bernoulli principle and related physical principles, or a similar structure. In addition, in other embodiments, the first gas acceleration device 206 may only include the contraction section, which may also serve to accelerate the gas.

[0223] Specifically, the gas medium physical parameter adjustment system 2061 includes multiple connecting pipes 2062 and valve assemblies. A plurality of holes are opened on the wall surface of the air inlet section of the first gas acceleration device 206, which are respectively connected to the multiple connecting pipes 2062. The valve assembly is arranged on the multiple connecting pipes 2062. The valve assembly includes but is not limited to one or more of a regulating valve, a constant pressure check valve and a variable pressure check valve. Different valves may be arranged on different connecting pipes 2062.

[0224] In a gas-cooled reactor, by setting a first gas acceleration device at the reactor coolant inlet, the flow rate of the gas medium in the gas-cooled reactor can be increased, thereby enhancing the gas medium circulation speed and efficiency; by setting a gas medium physical parameter adjustment system, the pressure and flow rate and other parameters of the gas medium in the air inlet section of the first gas acceleration device can be adjusted and changed according to different operating conditions of the reactor, such as different operating powers, thereby achieving automatic adjustment of the reactor cooling efficiency and tritium loading efficiency.

[0225] As shown in FIG6 , the reactor coolant inlet is connected to the core and the tritium production module system 204, respectively. The gas-cooled reactor includes a diverter plate 207, which is located between the first gas acceleration device 206 and the core 1014, and also between the first gas acceleration device 206 and the tritium production module system 204. The gas-cooled reactor is provided with a diverter plate to isolate the gas coolant entering the core from the gas medium entering the tritium production module system, so that the high-tritium gas medium does not mix into the core coolant after entering the tritium production module system, and maintains the tritium radioactivity level of the gas medium in the core coolant system.

[0226] In addition, in this embodiment, the gas parameters of the reactor coolant entering the core 1014 and the tritium production module system 204 can be adjusted respectively through the diverter plate 207.

[0227] As shown in Figure 1, the tritium production module system 204 includes a tritium production module system coolant inlet. After the reactor coolant is diverted by the diverter plate, a portion flows into the tritium production module system 204 through the tritium production module system coolant inlet. A second gas acceleration device 103 is provided at the tritium production module system coolant inlet.

[0228] The second gas acceleration device 103 has a structure with a variable cross-sectional area, and is not limited to a tubular structure or a plate-like structure with a variable cross-sectional area. It includes a contraction section, a narrow throat section, and an expansion section connected in sequence along the direction of gas flow. The cross-sectional area of ​​the contraction section decreases along the flow direction, and the cross-sectional area of ​​the expansion section increases along the flow direction. Preferably, the second gas acceleration device 103 has a Laval nozzle designed using the Bernoulli principle and related physical principles, or a similar structure. In addition, in other embodiments, the second gas acceleration device 103 may only include the contraction section, which can also serve to accelerate the gas.

[0229] As shown in Figure 6, the diverter plate 207 is preferably connected to the first gas accelerator 206, and the airflow rate can be controlled by adjusting the size of the opening at the junction of the diverter plate 207 and the first gas accelerator 206. Subsequently, based on the parameter range of the gas medium after passing through the first gas accelerator 206, the volume of the space between the diverter plate 207 and the reactor pressure vessel 1017 and other parameters can be adjusted to further adjust the coolant intake volume and parameters entering the core and the tritium production module system, respectively. By sequentially adjusting the gas parameters through the first gas accelerator 206 and the diverter plate 207, the reactor coolant entering the tritium production module system 204 can be coupled with the second gas accelerator 103, thereby enhancing the tritium-carrying capacity of the gas medium in the tritium production module system.

[0230] The specific structure of the tritium production module system 204 in this embodiment will be described in detail below:

[0231] As shown in FIG3 , the tritium production module system 204 includes a cladding 104 and a tritium production layer group. The cladding 104 is arranged at intervals along the radial direction of the gas-cooled reactor. The cladding 104 is located at the outermost layer of the tritium production module system along the radial direction of the reactor, and the tritium production layer group is located between the cladding 104. The tritium production layer group includes at least one of a tritium breeder layer 106 and a tritium breeder multiplication layer 107. Both the tritium breeder layer 106 and the tritium breeder multiplication layer 107 include a tritium production region, and the tritium production region includes tritium breeding material.

[0232] A first neutron multiplying layer 105 may also be provided in the tritium-producing layer group. The first neutron multiplying layer 105 comprises a neutron multiplying material. The first neutron multiplying layer 105 may be provided together with either or both of the tritium breeder layer 106 and the tritium breeder multiplying layer 107. Preferably, when the tritium-producing layer group contains only the tritium breeder layer 106, the first neutron multiplying layer 105 is also provided.

[0233] As shown in Figures 1 and 3, the tritium-producing layer group also includes a tritium pipe 101 for the circulation of reactor coolant and tritium-containing medium. The tritium pipe 101 extends along the axial direction of the gas-cooled reactor. A plurality of holes are opened on the wall of the tritium pipe 101, so that the interior of the tritium pipe 101 is fluidically connected to the tritium-producing area.

[0234] The tritium pipeline 101 is a single-layer or multi-layer pipeline. Preferably, the tritium pipeline 101 is a multi-layer pipeline, shown as a two-layer pipeline in Figure 1, with multiple holes provided in the wall of any one layer or any multiple layers of the multi-layer pipeline. Furthermore, preferably, along the extension direction of the tritium pipeline 101, the holes in any two adjacent layers of the pipeline wall are staggered. By configuring the tritium pipeline as a multi-layer pipeline and providing holes in the pipeline wall, as well as determining the location of the holes, the tritium production module system facilitates the release and diffusion of tritium from the tritium production module system into the tritium pipeline.

[0235] Furthermore, the tritium pipeline 101 is connected to the second gas acceleration device 103, which greatly increases the flow rate of the gas medium entering the tritium pipeline. It can improve the flow rate of the tritium medium in the tritium production module system 204, so that the flow rate, pressure, and density of the gas medium entering the different structural layers of the tritium production module system 204 are different, thereby enhancing the ability and efficiency of the gas medium to carry tritium. The ultrasonic vibrations generated at the same time can remove tritium deposited and attached to the flow channel wall and the tritium production module system 204, thereby reducing the sedimentation and adsorption loss of tritium. In addition, the second gas acceleration device 103 cooperates with the holes on the tube wall, so that the gas flow rate of the tritium pipeline 101 from the outside to the inner layer increases layer by layer and the pressure decreases layer by layer, thereby further enhancing the efficiency of tritium release and diffusion into the tritium pipeline.

[0236] As shown in Figures 1 and 3, in this embodiment, the tritium-producing layer group includes a first neutron multiplying layer 105 and a tritium breeder layer 106 arranged radially along the gas-cooled reactor. The tritium breeder layer 106 is located outside the first neutron multiplying layer 105, and at least a portion of the tritium pipe 101 is located inside the tritium breeder layer 106.

[0237] The tritium production module system 204 further includes partitions 109 . Partitions 109 are provided between different types of layers in the tritium production layer group, and partitions 109 may also be provided between the tritium production layer group and other layers.

[0238] In some other embodiments, the tritium production layer group includes a first circulation structure in which the first neutron multiplying layer 105 and the tritium breeding layer 106 arranged radially along the reactor are circulated multiple times, and partitions 109 may be provided between different layers in the tritium production layer group. This circulation structure can enhance the utilization rate of neutrons in the tritium production module system.

[0239] The tritium production module system 204 also includes a tritium-proof layer, adjacent to the cladding 104. The layer is a coating or low-permeability structure. The layer comprises an oxide and a titanium-containing ceramic. The oxide may comprise one or more of the following: Cr2O3, Al2O3, and Ti2O2. The titanium-containing ceramic is preferably titanium aluminum carbide. The layer effectively prevents tritium from penetrating outside the tritium production module system and causing loss.

[0240] The cladding material includes, but is not limited to, one or more of the following: austenitic stainless steel, martensitic stainless steel, ferritic steel, vanadium alloy, zirconium alloy, copper alloy, titanium alloy. Preferably, the cladding thickness is 5 mm to 30 mm.

[0241] The tritium production module system 204 also includes an irradiation product production layer 1011. The materials of the irradiation product production layer 1011 include one or more of the following substances: Np-237 and its compounds for producing Pu-238, and Co-59 and its compounds for producing Co-60. Baffles 109 are provided on both sides of the irradiation product production layer 1011, and the irradiation product production layer 1011 is located outside the tritium breeder layer 106. For other embodiments requiring irradiation product production, the irradiation product production layer 1011 may also be located elsewhere in the tritium breeder layer 106, including radially inward or circumferentially along the gas-cooled reactor.

[0242] Tritium production module system 204 also includes a first reflector or first moderator layer 1010, located outside irradiation product production layer 1011. The material of first reflector or first moderator layer 1010 includes one or more of the following: graphite, isostatically pressed graphite, nuclear-grade graphite, boron carbide, silicon carbide, boron-containing silicon carbide, beryllium oxide, or a beryllium-containing compound. The reflector layer reflects neutrons, improving neutron utilization and increasing tritium production.

[0243] In some other embodiments, the irradiated product production layer 1011 can also be placed between any two layers of the first neutron multiplying layer, the tritium breeding layer, the tritium breeding multiplying layer, the first moderator layer or the first reflector layer, and partitions are set between the irradiated product production layer and other layers.

[0244] To sum up, preferably, in this embodiment, the tritium production module system includes a cladding 104, a tritium penetration prevention layer, a first neutron multiplying layer 105, a partition 109, a tritium breeding layer 106, a partition 109, an irradiated product production layer 1011, a partition 109, a first reflection layer or a first moderator layer 1010, a tritium penetration prevention layer, and a cladding 104, which are arranged in sequence from the inside to the outside along the radial direction of the reactor.

[0245] Specifically, the first neutron multiplying layer 105 and the tritium breeding layer 106 both employ a structure of material balls filled in a ball bed. The first neutron multiplying layer includes neutron multiplying material balls, each containing a neutron multiplying material, which includes beryllium and beryllium-containing compounds, such as beryllium, BeO, or beryllium-containing ceramics.

[0246] The tritium breeding layer 106 includes a tritium breeding material ball. The tritium breeding material ball contains tritium breeding material. The tritium breeding material includes one or a mixture of the following substances: Li2O, Li2TiO3, LiAlO2, Li4SiO4, and Li2ZrO3 ceramics.

[0247] The diameter of the neutron multiplication material balls and tritium breeding material balls is 0.1mm-10mm, and the filling rate is 40%-80%. Preferably, the diameter is 0.2mm-2mm, and the filling rate is 50%-70%, to achieve better neutron multiplication and tritium breeding effects.

[0248] Preferably, the enrichment of Li-6 in the tritium breeder material is 7.5%-90%, and the enrichment of Li-7 is 10%-92.5%, with the total enrichment of Li-6 and Li-7 being 100%. Tritium breeder material with a Li-7 enrichment of 50%-92.5% is positioned close to the reactor core, while tritium breeder material with a Li-6 enrichment of 50%-90% is positioned away from the core.

[0249] Fast neutrons with energies greater than 1.0 MeV, which have a higher proportion in the hard neutron energy spectrum near the core, react with Li-7 to produce tritium (Li-7 has a large cross-section for fast neutrons with an energy of 2.47 MeV). By slowing down the neutrons through the previous material layer, the neutron energy spectrum is "softened" to increase the proportion of low-energy and thermal neutrons, thereby increasing the tritium production rate with Li-6, ultimately reducing the manufacturing cost of the breeding material and improving the tritium production rate.

[0250] The tritium production module system also includes a coolant channel, which has a similar function to the tritium pipe and is used for the circulation of reactor coolant and / or tritium-containing medium. The coolant channel is arranged in the gaps between the layers of the tritium production module system and / or inside the cladding and / or partitions.

[0251] Preferably, the thickness of the cladding and / or the partition is greater than 1 mm. If coolant pipes are provided in the cladding and / or the partition, the thickness of the cladding and / or the partition with the coolant channels is greater than 3 mm.

[0252] The tritium production module system can be completely or partially surrounded by the periphery of the core in the circumferential direction. The periphery of the core can include multiple tritium production module systems with the same or different structures. The multiple tritium production module systems can be evenly or unevenly arranged within a 360° angle range, or evenly or unevenly arranged at certain angles within a partial angle range of the periphery of the core.

[0253] The shape of the tritium production module system includes one or more of the following shapes: 360° overall hollow circular cylinder, hollow arc cylinder within an angle of 1° to 359°, cylinder, polygonal prism, trapezoidal cross-section cylinder, fan-shaped cross-section cylinder, and cube.

[0254] In the present application, the thickness of the tritium production module system along the radial direction of the reactor is 1 cm to 100 cm. Preferably, the thickness of the tritium production module system is 15 cm to 60 cm.

[0255] Preferably, as shown in Figure 3, the tritium production module system is shaped like a circular cylinder, completely surrounding the reactor core circumferentially. The tritium production module system is composed of multiple tritium production submodules seamlessly joined circumferentially, with the number of tritium production submodules ranging from 4 to 24. Specifically, the tritium production submodules are shaped like a cylinder with a sector cross-section angled between 15° and 90°.

[0256] Further preferably, as shown in Figure 3, partitions are provided between adjacent tritium-producing submodules to prevent direct contact between materials in adjacent tritium-producing submodules. Tritium conduits are arranged circumferentially around the core in the tritium breeding layer, with 2-6 tritium conduits provided in each tritium-producing submodule.

[0257] This tritium production module system is completely surrounded by the reactor in the circumferential direction and is composed of a certain number of tritium-producing daughter modules, so that the reactor can achieve the maximum tritium production effect. When problems occur in some tritium-producing daughter modules, they can be easily replaced, thereby ensuring the stability of the reactor's tritium production.

[0258] As shown in Figure 6, the core 1014 includes fuel assemblies 2011. Along the axial direction of the gas-cooled reactor, fuel assemblies 2011 are divided into multiple sections. The fissile nuclide enrichment of fuel assemblies 2011 increases from the inlet to the outlet. Temperature and pressure differentials increase the flow rate of the flow channel gas in the core and fuel assemblies, improving core cooling efficiency and flattening the axial power distribution of the fuel assemblies, enhancing core safety.

[0259] Preferably, the fuel assembly 2011 is divided into 3-8 sections along the axial direction of the gas-cooled reactor, and the multi-section fuel assembly 2011 uses 3-4 types of fuels with different enrichment levels of fissile nuclides.

[0260] Preferably, fuel assembly 2011 includes a fuel assembly coolant flow channel, equipped with a third gas accelerator 2012. Third gas accelerator 2012 utilizes a structure similar to first gas accelerator 206 and second gas accelerator 103, employing a variable cross-sectional area structure, including a contracting section, or a contracting section, a narrow throat section, and a diverging section sequentially connected along the gas flow direction. Preferably, a Laval nozzle structure can be employed. The third gas accelerator is designed into the fuel assembly coolant flow channel to further increase the coolant gas flow rate and enhance the cooling efficiency of the fuel.

[0261] It should be noted that the above scheme of segmenting the fuel assembly and providing the third gas acceleration device 2012 is more suitable for high-flux gas-cooled reactors or high-flux gas-cooled fast reactors, and may not be adopted for other types of gas-cooled reactors.

[0262] A coolant flow channel and / or a second neutron multiplying layer and / or a second reflective layer and / or a second moderator layer may be arranged between the nuclear fuel sealing isolation layer 1016 and the tritium production module system 204; a coolant flow channel and / or a third neutron multiplying layer and / or a third reflective layer and / or a third moderator layer may be arranged between the reactor pressure vessel 1017 and the tritium production module system 204.

[0263] The nuclear fuel containment barrier 1016 comprises a metal container or enclosure, as well as fixed support members. As shown in FIG7 , a neutron conditioning layer 1015 is disposed between the core 1014 and the nuclear fuel containment barrier 1016. The neutron conditioning layer 1015 comprises coolant channels, a fourth neutron multiplying layer, a fourth reflector layer, and / or a fourth moderator layer.

[0264] For a general gas-cooled reactor, a fourth neutron multiplying layer is provided in the neutron regulating layer 1015. For a cold fast reactor, the neutron regulating layer 1015 of the gas-cooled reactor may be provided as a fourth moderator layer.

[0265] The thermal neutron flux rate of the tritium production module system 204 of the gas-cooled reactor is 1.0×10 10 ~2.0×10 13 n / cm 2 ·s, and the fast neutron flux rate was 5.0×10 9 ~5.0×10 12 n / cm 2 ·s; if the gas-cooled reactor 100 is a gas-cooled fast reactor, the thermal neutron flux rate of the tritium production module system 4 is 1.0×10 10 ~2.0×10 13 n / cm 2 ·s, and the fast neutron flux rate was 5.0×10 9 ~1.0×10 13 n / cm 2 ·s.

[0266] The reactor coolant is a gas, and the cooling gas includes an inert gas such as helium (He), or a gas with stable physical and chemical properties such as carbon dioxide (CO2). Preferably, the reactor coolant gas is an inert gas such as helium (He).

[0267] Fuel element shapes include: spherical, cylindrical, plate-like, block-like, cross-plate-like, curved plate-like, and hollow cylindrical. The cross-sectional shapes of cylindrical fuel elements include: circular, regular polygonal (such as square, regular hexagon, regular octagon, etc.). The inner and outer cross-sectional shapes of hollow cylindrical fuel elements include: circular, regular polygonal (such as square, regular hexagon, regular octagon, etc.), and the inner and outer shapes can be the same or different.

[0268] The core fuel is a material containing uranium, thorium, or plutonium, including AO2, AC, AN, or MOX ceramic fuel, or TRISO-type fuel coated with particles. A is one of uranium, thorium, and plutonium, and MOX includes any two or three of these.

[0269] Gas-cooled reactors and gas-cooled fast reactors use uranium fuel or uranium-thorium MOX fuel, with the U-235 enrichment of not less than 4.5%; if uranium-plutonium MOX fuel, thorium-plutonium MOX fuel or uranium-thorium-plutonium MOX fuel is used, the Pu-239 enrichment of not less than 5%.

[0270] Example 5:

[0271] The structure of the gas-cooled reactor in this embodiment is essentially the same as that in Example 4, differing only in the structure of the tritium production module system 204. As shown in Figure 4 , the tritium production module system in this embodiment comprises a cladding 104 and a tritium multiplication layer 107 between the claddings. A tritium-proof layer may also be provided adjacent to the cladding 104.

[0272] Specifically, the tritium-producing layer group in this embodiment includes a tritium multiplication layer 107, which includes a neutron multiplication section 1012 and a cylindrical tritium multiplication section 1013. Multiple tritium multiplication sections 1013 are evenly arranged within the neutron multiplication section 1012, ensuring that the neutron flux within each tritium multiplication section 1013 is at the same order of magnitude. Preferably, a partition 109 is disposed around the cylindrical tritium multiplication section 1013 to separate the materials of the neutron multiplication section 1012 from those of the tritium multiplication section 1013. The volume ratio of the neutron multiplication section 1012 to the tritium multiplication section 1013 is within a range of 2:1 to 8:1. The tritium conduits 101 are arranged in an array within the tritium multiplication section 1013.

[0273] Preferably, the number of tritium breeding sections 1013 in each tritium-producing submodule does not exceed six, and as shown in FIG4 , there are three. This ensures that the distance difference between the material at all locations within the tritium breeding section 1013 and the nearest tritium pipe 101 does not exceed 50% of the diameter of the tritium breeding section 1013, thereby facilitating the release and diffusion of tritium in the tritium breeding section 1013.

[0274] In some other embodiments, the tritium-producing layer group includes a second circulation structure, in which the first neutron multiplying layer 105, tritium breeder layer 106, and tritium multiplication layer 107, arranged radially along the reactor, circulate multiple times. Partitions 109 may be provided between the different layers. The shapes and structures of the first neutron multiplying layer 105 and tritium breeder layer 106 are described in Example 4. This circulation structure improves neutron utilization within the reactor.

[0275] In some other embodiments, the tritium-producing layer group may be configured as a combination of the tritium breeding multiplication layer 107 and the first neutron multiplication layer 105 .

[0276] Specifically, the tritium multiplication layer 107 can be configured as a mixture of neutron multiplication material balls and tritium multiplication material balls. The tritium multiplication layer 107 can also include tritium multiplication material balls, the core of the tritium multiplication material balls has tritium multiplication material, and the shell of the tritium multiplication material balls has neutron multiplication material.

[0277] If tritium multiplication layer 107 is a mixture of neutron multiplication material balls and tritium multiplication material balls, the ratio of neutron multiplication material balls to tritium multiplication material balls is within a range of 2:1 to 8:1. The diameter of the neutron multiplication material balls, tritium multiplication material balls, or tritium multiplication material balls is 0.1 mm to 10 mm, and the filling rate is 40% to 80%. Preferably, the diameter is 0.2 mm to 2 mm, and the filling rate is 50% to 70%. This achieves better neutron multiplication and tritium multiplication effects.

[0278] It should be noted that the structure of the tritium multiplication layer 107 described in this embodiment is only preferred and is not limited to the structure described in Figure 10. For example, the cross-sectional shape of the tritium multiplication portion 1013 can be other shapes, or the tritium multiplication layer 107 can only include tritium multiplication material balls.

[0279] In this embodiment, preferably, the irradiated product production layer 1011 is not provided. Furthermore, by utilizing the neutron multiplication unit 1012 as a neutron reflector, the tritium production module system can be provided without the first reflector layer or the first moderator layer 1010. This greatly simplifies the structure of the tritium production module system.

[0280] In addition, in order to take isotope production into consideration, no more than one-half of the total amount of materials in the tritium breeding section 1013 can be filled with isotope production materials.

[0281] In some other embodiments, an irradiation product production layer 1011 or a first reflection layer or a first moderation layer 1010 may also be provided in the tritium production module system described in this embodiment.

[0282] In summary, from the above description, it can be seen that Example 4 and Example 5 achieve at least the following technical effects:

[0283] 1. In a gas-cooled reactor, by installing a tritium production module system outside the core to produce tritium, the radiation hazard to reactor components, external personnel, and equipment caused by neutron leakage from the gas-cooled reactor core can be resolved, and the thickness of the gas-cooled reactor's reflector layer, moderator layer, and external shield can be reduced. 2. In a gas-cooled reactor, by installing a first gas accelerator at the reactor coolant inlet, the flow rate of the gas medium within the gas-cooled reactor can be increased, thereby enhancing the gas medium circulation speed and efficiency. By setting up a gas medium physical parameter adjustment system, the pressure and flow rate of the gas medium in the inlet section of the first gas accelerator can be adjusted according to different reactor operating conditions, such as different operating powers, thereby achieving automatic adjustment of the reactor cooling efficiency and tritium loading efficiency. 3. The gas-cooled reactor, by installing a second gas accelerator at the coolant inlet of the tritium production module system, can increase the flow rate of the tritium-containing medium within the tritium production module system, so that the flow rate, pressure, and density of the gas medium entering different structural layers of the tritium production module system are different, thereby enhancing the gas medium's ability and efficiency to carry tritium. At the same time, the ultrasonic vibrations generated can remove tritium deposited and attached to the flow channel walls and within the tritium production module system, thereby reducing tritium sedimentation and adsorption losses. 4. The gas-cooled reactor, by installing a diverter plate, separates the gas coolant entering the core from the gas medium entering the tritium production module system, preventing the high-tritium gas medium from mixing with the core coolant after entering the tritium production module system, thereby maintaining the tritium radioactivity level of the gas medium in the core coolant system. The gas medium parameters entering different systems are separately adjusted, so that the reactor coolant entering the tritium production module system couples with the second gas accelerator, thereby enhancing the gas medium's ability to carry tritium in the tritium production module system. 5. The tritium production module system of the gas-cooled reactor can better realize the functions of neutron multiplication and tritium production by designing the structure of the neutron multiplying layer, the tritium breeding layer or the structure of the tritium breeding multiplication layer. In addition, the position and structure of the tritium pipeline in the tritium production module system can be designed to enhance the transfer capacity and efficiency of tritium in the tritium production module system.

[0284] Example 6:

[0285] The structure of the gas-cooled reactor in this embodiment is substantially the same as that in Embodiments 4 and 5, as shown in FIG8 . Here, a gas-cooled reactor substantially identical to the tritium production module system 204 in Embodiment 4 is used as an example. The difference is that the gas-cooled reactor in this embodiment is a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor.

[0286] Specifically, to further increase the neutron fluence rate at the tritium production module system, it is preferred that the core 1014 utilize arc-shaped, columnar fuel elements arranged in a compact array. For high-flux gas-cooled reactors, coolant channels can be provided in the neutron conditioning layer 1015. For high-flux gas-cooled fast reactors, coolant channels can be provided in the neutron conditioning layer 1015, and a fourth moderator or reflector layer can be provided.

[0287] Furthermore, for high-flux gas-cooled reactors and high-flux gas-cooled fast reactors, the core uses uranium fuel with an enrichment of U-235 of not less than 15%, or MOX fuel with an enrichment of U-235 of 0.3% and an enrichment of Pu-239 of not less than 10%.

[0288] As shown in FIG6 , the core 1014 includes a fuel assembly 2011 . The fuel assembly 2011 is divided into multiple sections along the axial direction of the gas-cooled reactor. The fissile nuclide enrichment of the fuel assembly 2011 increases section by section from the air inlet end to the air outlet end of the fuel assembly 2011 .

[0289] Preferably, the fuel assembly 2011 is divided into 3-8 sections along the axial direction of the gas-cooled reactor, and the multi-section fuel assembly 2011 uses 3-4 types of fuels with different enrichment levels of fissile nuclides.

[0290] By designing fuel assemblies in high-flux gas-cooled reactors or high-flux gas-cooled fast reactors to be divided into multiple sections along the axial direction and using fuels with different enrichments of fissile nuclides, the flow rate of the flow channel gas in the core and fuel assemblies is increased through temperature and pressure differences, thereby improving the core cooling efficiency, flattening the axial power distribution of the fuel assemblies, and enhancing core safety.

[0291] Preferably, fuel assembly 2011 includes a fuel assembly coolant flow channel, on which a third gas accelerator 2012 is disposed. Third gas accelerator 2012 employs a structure similar to first gas accelerator 206 and second gas accelerator 103, preferably employing a Laval nozzle structure. The third gas accelerator is designed into the fuel assembly coolant flow channel to further increase the coolant gas flow rate and enhance the cooling efficiency of the fuel.

[0292] As shown in Figure 8, the fuel assembly 2011 is cylindrical and includes multiple fuel elements 2013. The fuel assembly is divided into multiple layers along the radial direction of the gas-cooled reactor. The fuel assembly coolant flow channels include interlayer flow channels, which are the 2mm to 20mm gaps between different layers of fuel assemblies 2011.

[0293] Furthermore, the fuel assembly 2011 is further divided into multiple sectors along the circumferential direction of the gas-cooled reactor. The angles of each sector can vary, so that each layer of fuel assembly 2011 has multiple fuel elements 2013. The fuel assembly coolant flow path also includes axial channels, and each fuel element 2013 has multiple axial channels along the axial direction of the gas-cooled reactor.

[0294] Specifically, the number of axial holes on each fuel element 2013 is determined according to the following formula: Where n is the number of axial channels, θ is the central angle of the sector in which the fuel element 2013 is located, and m is the number of layers in which the fuel element 2013 is located, from the inside outward along the radial direction of the gas-cooled reactor. This design ensures that each fuel element has an appropriate number of axial channels, thereby improving the cooling efficiency of the entire fuel assembly 2011.

[0295] By designing the shape of the fuel assembly coolant flow channel and designing a third gas accelerator in the fuel assembly coolant flow channel in a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor, the coolant gas flow rate is further increased, and the cooling efficiency of the fuel is enhanced, thereby achieving the tritium production capability under high neutron injection and high temperature conditions in the high-flux gas-cooled reactor or the high-flux gas-cooled fast reactor.

[0296] The thermal neutron flux rate of the tritium production module system 204 of the high flux gas-cooled reactor is 1.0×10 11 ~5.0×10 15 n / cm 2 ·s, and the fast neutron flux rate is 1.5×10 10 ~1.0×10 15 n / cm 2 ·s; the thermal neutron flux rate of the tritium production module system 204 of the high-flux gas-cooled fast reactor is 1.0×10 11 ~5.0×10 15 n / cm 2 ·s, the fast neutron flux rate is 3×10 12 ~5.0×10 15 n / cm 2 ·s.

[0297] In summary, from the above description, it can be seen that this embodiment 6 also achieves at least the following technical effects:

[0298] 1. By designing fuel assemblies in a high-flux gas-cooled reactor (HFR) or a high-flux gas-cooled fast reactor (HFR) to be divided into multiple axial segments and using fuels with varying fissile nuclides enrichment, the gas flow rate in the core and fuel assemblies is increased through temperature and pressure differences, improving core cooling efficiency while flattening the axial power distribution of the fuel assemblies and enhancing core safety. 2. By designing the shape of the fuel assembly coolant flow channels in a HFR or a HFR and designing a third gas accelerator in the fuel assembly coolant flow channels, the coolant gas flow rate is further increased, enhancing fuel cooling efficiency and achieving tritium production capability under high neutron flux and high temperature conditions. 3. By providing a first gas accelerator in the gas-cooled reactor, coolant flow channels in the core and fuel assemblies, and a third gas accelerator, efficient core cooling is ensured, and the temperature of the gas-cooled reactor fuel and internal component materials is controlled, thereby achieving HFR technology.

[0299] Example 7:

[0300] Based on Example 4, Example 5 and Example 6, this example further proposes a combined system of a gas-cooled reactor and a fusion reactor, as shown in Figure 9, which includes any one of the gas-cooled reactors 1 in Example 4, Example 5 or Example 6, and also includes a fusion reactor 2.

[0301] It should be noted that the fusion reactor 2 mentioned in this application includes all fusion reactors using tritium and / or helium-3 (He-3) as fusion fuel and fusion-fission hybrid reactors.

[0302] The combined system further includes a tritium supply system 3 , which is connected to the gas-cooled reactor 1 and also to the fusion reactor 2 . The gas-cooled reactor 1 produces tritium and provides tritium fuel and / or helium-3 fuel to the fusion reactor 2 .

[0303] This combined system sets up a tritium supply system to collect, process, store and transport the tritium produced by the gas-cooled reactor through the tritium supply system, and can provide tritium and / or helium-3 as fuel to fusion reactors or fusion-fission hybrid reactors, thereby solving the problems of tritium self-sustaining and fuel replenishment in fusion reactors and fusion-fission hybrid reactors.

[0304] Specifically, the tritium supply system 3 includes a tritium collection system 3-A, a tritium processing and storage system 3-B, and a tritium fuel replenishment system 3-C, which are connected in sequence. The tritium collection system 3-A is connected to the gas-cooled reactor 1, and the tritium fuel replenishment system 3-C is connected to the fusion reactor 2.

[0305] The tritium processing and storage system 3-B includes: tritium extraction system 3-B1, tritium purification and separation system 3-B2, tritium storage system 3-B3 and tritium monitoring system; the tritium monitoring system is associated with the tritium extraction system 3-B1, tritium purification and separation system 3-B2 and tritium storage system 3-B3, and monitors the equipment and facilities of each system.

[0306] The "association" here means that there is a physical connection, wireless communication connection or data transmission connection between the equipment in the tritium monitoring system and the equipment to be monitored in each subsystem of the tritium processing and storage system 3-B, so as to realize different monitoring functions.

[0307] The tritium collection system 3-A includes a tritium purification system, a tritium diversion system, a gas cooling system, and a tritium conversion / catalysis system. The tritium fuel replenishment system 3-C includes a fuel pretreatment system and a tritium injection system, which is connected to the fusion reactor 2. The fuel pretreatment system separates the tritium fuel and helium-3 fuel, and the tritium injection system injects them into the fusion reactor 2.

[0308] As shown in FIG9 , the input of the tritium collection system 3 -A is connected to the tritium production module system 1 -A of the gas-cooled reactor 1 , and the reactor coolant and tritium-containing medium in the tritium production module system 204 enter the tritium supply system 3 .

[0309] Furthermore, the input of the tritium collection system 3-A is connected to the core 1-B of the gas-cooled reactor 1, and the reactor coolant in the core 1014 enters the tritium supply system 3. The reactor coolant after separation and purification to remove tritium is returned to the gas-cooled reactor 1 for reuse.

[0310] This combined system connects the tritium collection system's input to the gas-cooled reactor's tritium production module system and the reactor core. When there is no need to extract or purify the core coolant for tritium, only the connection between the tritium production module system and the tritium collection system can be opened. The reactor coolant, after separation and purification to remove tritium, can be returned to the gas-cooled reactor for reuse, thereby improving economic efficiency.

[0311] The combined system also includes a fission fuel bidirectional supply system 4, comprising a first nuclear fuel supply system 4-A and a second nuclear fuel supply system 4-B. Through the fission fuel bidirectional supply system 4, the gas-cooled reactor 1 and the fusion reactor 2 supply nuclear fuel to each other. The nuclear fuel here may include fission fuel, conversion fuel, or fusion fuel.

[0312] Specifically, the gas-cooled reactor 1 provides the fusion reactor 2 with one or more of the following materials via the first nuclear fuel supply system 4-A: depleted uranium, Th-232, U-238, and Pu-239 initial fuel. These materials may be used as conversion fuel for the fusion reactor or fissile material for a fusion-fission hybrid reactor.

[0313] The fusion reactor 2 supplies Pu-239 and / or U-233 to the gas-cooled reactor 1 via the second nuclear fuel supply system 4-B. The Pu-239 is used as MOX fuel for the gas-cooled reactor.

[0314] Specifically, the first nuclear fuel supply system 4-A includes a spent fuel receiving and dissolution unit, a spent fuel and isotope separation and purification unit, a nuclide extraction unit, and a fusion reactor or hybrid reactor nuclear fuel manufacturing unit, which are connected in sequence.

[0315] The second nuclear fuel supply system 4-B includes a nuclear fuel cladding receiving and disintegration unit, a cladding shearing and decomposition unit, a nuclide separation and purification unit, and a gas-cooled reactor nuclear fuel manufacturing unit, which are connected in sequence.

[0316] The first nuclear fuel supply system 4-A and the second nuclear fuel supply system 4-B also include a radioactive waste treatment and storage unit and a tritium enrichment unit. The high-tritium waste liquid and waste gas generated by the radioactive waste treatment and storage unit and the tritium in the tritium enrichment unit are transported to the tritium collection system or the tritium treatment and storage system.

[0317] This combined system sets up a two-way fission fuel supply system, so that the gas-cooled reactor and fusion reactor inside the combined system can provide each other with nuclear fuel, achieving the goal of symbiosis of gas-cooled reactor and fusion reactor or fusion-fission hybrid reactor, increasing the utilization rate of fission fuel, reducing total radioactive waste, and enhancing the economy of the combined system.

[0318] In summary, from the above description, it can be seen that this embodiment 7 achieves at least the following technical effects:

[0319] 1. This combined system utilizes a tritium supply system to collect, process, store, and transport tritium produced by the gas-cooled reactor. This system can then provide tritium fuel and / or helium-3 fuel to fusion reactors or fusion-fission hybrid reactors, addressing the challenges of tritium self-sustaining and fuel replenishment in these reactors. 2. This combined system utilizes a bidirectional fission fuel supply system, enabling the gas-cooled reactor and fusion reactor within the combined system to mutually supply nuclear fuel, achieving the goal of symbiosis between the gas-cooled reactor and the fusion reactor or fusion-fission hybrid reactor. This increases fission fuel utilization, reduces total radioactive waste, and enhances the economic efficiency of the combined system. 3. This combined system connects the tritium collection system's input to the gas-cooled reactor's tritium production module system and the reactor core. When there is no need to extract or purify the core coolant, only the tritium production module system and the tritium collection system can be connected. The reactor coolant, after separation and purification to remove tritium, can be returned to the gas-cooled reactor for reuse, thereby improving economic efficiency.

[0320] Example 8:

[0321] This embodiment proposes a combined gas-cooled reactor and fusion reactor system, as shown in FIG9 . The system includes a gas-cooled reactor 1 and a fusion reactor 2. It also includes a tritium fuel supply system 3, which is connected to both the gas-cooled reactor 1 and the fusion reactor 2. The gas-cooled reactor 1 generates tritium and introduces a coolant and a gaseous medium containing tritium into the tritium fuel supply system 3 to produce tritium and / or helium-3 fuel. The tritium fuel and / or helium-3 fuel is then delivered to the fusion reactor 2.

[0322] It should be noted that all fusion reactors 2 mentioned in this application include all fusion reactors using tritium and / or helium-3 (He-3) as fusion fuel and fusion-fission hybrid reactors.

[0323] The combined system also includes a bidirectional fission fuel supply system 4, connected to both the gas-cooled reactor 1 and the fusion reactor 2. This system includes a first nuclear fuel and isotope reprocessing system 4-A and a second nuclear fuel and isotope reprocessing system 4-B. Through bidirectional fission fuel supply system 4, the gas-cooled reactor 1 and the fusion reactor 2 supply nuclear fuel to each other. This nuclear fuel may include fission fuel, conversion fuel, or fusion fuel.

[0324] Specifically, the tritium fuel supply system 3 includes a tritium collection system 3-A, a tritium processing and storage system 3-B, and a tritium replenishment system 3-C, which are connected in sequence, wherein the tritium collection system 3-A is connected to the gas-cooled reactor 1, and the tritium replenishment system 3-C is connected to the fusion reactor 2.

[0325] Furthermore, the tritium processing and storage system 3-B includes a tritium extraction subsystem 3-B1, a tritium purification and separation subsystem 3-B2, a tritium storage subsystem 3-B3, and a tritium monitoring subsystem. The tritium monitoring subsystem is associated with each of these subsystems, monitoring the equipment and facilities within them.

[0326] The association here means that the equipment in the tritium monitoring subsystem has a physical connection, wireless communication connection or data transmission connection with the equipment to be monitored in other subsystems of the tritium treatment and storage system 3-B, thereby realizing different monitoring functions.

[0327] It should be noted that the way in which the tritium extraction subsystem 3-B1, the tritium purification and separation subsystem 3-B2, and the tritium storage subsystem 3-B3 are connected in sequence in Figure 9 is only for reference. In actual applications, there is no fixed order restriction for the equipment and facilities in the tritium extraction subsystem 3-B1, the tritium purification and separation subsystem 3-B2, and the tritium storage subsystem 3-B3.

[0328] The tritium collection system 3-A includes a tritium purification subsystem, a tritium diversion subsystem, and a gas cooling and tritium conversion / catalysis subsystem. The tritium purification subsystem is connected to the gas-cooled reactor 1. The gas coolant and tritium-containing medium in the gas-cooled reactor are introduced into the tritium purification subsystem.

[0329] The tritium replenishment system 3-C includes a fuel preconditioning unit 3-15 and a tritium injection unit 3-16. The tritium injection unit 3-16 is connected to the fusion reactor 2. The fuel preconditioning unit 3-15 includes equipment for separating tritium and helium-3. After separation, the tritium fuel and helium-3 fuel are respectively introduced into the tritium injection unit 3-16. The tritium injection unit 3-16 injects the tritium fuel and / or helium-3 fuel into the fusion reactor 2 for the primary reaction.

[0330] The combined system of the present application sets up a tritium supply system and designs the specific composition and structure of the tritium supply system. The tritium produced by the gas-cooled reactor is collected, processed, stored and transported in the tritium supply system to obtain tritium fuel and / or helium-3 fuel, which is then provided to the fusion reactor to solve the problem of tritium self-sustaining and fuel replenishment of the fusion reactor.

[0331] The fission fuel bidirectional supply system 4 includes a first nuclear fuel and isotope reprocessing system 4-A connected to both the gas-cooled reactor 1 and the fusion reactor 2. Through this first nuclear fuel and isotope reprocessing system 4-A, the gas-cooled reactor 1 provides the fusion reactor 2 with one or more of the following materials: depleted uranium, Th-232, U-238, and Pu-239 initial fuel. These materials may be used as conversion fuel for the fusion reactor or fissile material for a fusion-fission hybrid reactor.

[0332] In addition, the bidirectional fission fuel supply system 4 also includes a second nuclear fuel and isotope reprocessing system 4-B connected to both the gas-cooled reactor 1 and the fusion reactor 2. Through this second nuclear fuel and isotope reprocessing system 4-B, the fusion reactor 2 supplies Pu-239 and / or U-233 to the gas-cooled reactor 1. The Pu-239 is used as MOX fuel for the gas-cooled reactor.

[0333] In the present application, in addition to the gas-cooled reactor 1 providing tritium fuel and / or helium-3 fuel to the fusion reactor 2 through the tritium supply system, and the gas-cooled reactor 1 and the fusion reactor 2 providing nuclear fuel to each other through the fission fuel bidirectional supply system, preferably, when the fusion reactor 2 is operated in pulsed mode, the gas-cooled reactor 1 can provide energy and power to the fusion reactor 2.

[0334] As shown in Figure 11, specifically, the first nuclear fuel and isotope reprocessing system 4-A includes a spent fuel receiving and dissolution unit 4-1, a spent fuel and isotope separation and purification unit 4-2, a nuclide extraction unit 4-3, and a fusion reactor nuclear fuel manufacturing unit 4-4, which are connected in sequence, wherein the spent fuel receiving and dissolution unit 4-1 is connected to the gas-cooled reactor 1, and the fusion reactor nuclear fuel manufacturing unit 4-4 is connected to the fusion reactor 2.

[0335] The second nuclear fuel and isotope reprocessing system 4-B includes a nuclear fuel cladding receiving and disintegration unit 4-5, a cladding shearing and decomposition unit 4-6, a nuclide separation and purification unit 4-7, and a gas-cooled reactor nuclear fuel manufacturing unit 4-8, which are connected in sequence, wherein the nuclear fuel cladding receiving and disintegration unit 4-5 is connected to the fusion reactor 2, and the gas-cooled reactor nuclear fuel manufacturing unit 4-8 is connected to the gas-cooled reactor 1.

[0336] Furthermore, both the first nuclear fuel and isotope reprocessing system 4-A and the second nuclear fuel and isotope reprocessing system 4-B include radioactive waste treatment and storage units and tritium enrichment units. The highly tritium-rich waste liquid and gas produced by the radioactive waste treatment and storage units, as well as the tritium-containing material in the tritium enrichment units, are transported to the tritium collection system 3-A and / or the tritium treatment and storage system 3-B. Connecting the bidirectional fission fuel supply system 4 and the tritium fuel supply system 3 fully utilizes the tritium in the bidirectional fission fuel supply system 4, thereby improving the economic efficiency of the combined system.

[0337] The combined system of the present application sets up a two-way fission fuel supply system, so that the gas-cooled reactor and fusion reactor within the combined system can provide nuclear fuel to each other, achieving the goal of joint symbiosis of the gas-cooled reactor and the fusion reactor, increasing the utilization rate of the fission fuel, reducing the total radioactive waste, and enhancing the economy and environmental friendliness of the combined system.

[0338] As shown in FIG9 , the gas-cooled reactor 1 includes a tritium production module system 204 and a core 1014. The tritium production module system 204 is disposed outside the core 1014 and includes tritium breeding material, which reacts with neutrons in the core 1014 to produce tritium. The main factors contributing to tritium production in the core 1014 are tritium produced by the fission of the core nuclear fuel (ternary), the reaction of He-3 in the coolant with neutrons, the reaction of B-10 in materials (primarily graphite) with neutrons, and the reaction of Li produced by the reaction of C-12 in graphite with neutrons, which in turn reacts with neutrons to produce tritium.

[0339] The input of the tritium purification subsystem is connected to the tritium production module system 204, or the input of the tritium purification subsystem is respectively connected to the tritium production module system 204 and the core 1014. When tritium extraction or tritium purification of the core coolant is not required, only the connection between the tritium production module system and the tritium collection system can be opened.

[0340] The reactor coolant purified by the tritium collection system 3-A or purified and separated by the tritium treatment storage system 3-B can be returned to the gas-cooled reactor for reuse, thereby improving economic efficiency.

[0341] As shown in FIG10 , the specific design of the tritium fuel supply system 3 is described below:

[0342] When the tritium content in the reactor coolant reaches the purification threshold, the reactor gas coolant of the core 1014 and the gas medium in the tritium production module system 204 flow into the tritium fuel supply system 3, first into the tritium purification subsystem.

[0343] The tritium purification subsystem includes a dust and aerosol filter unit 3-1, a radioactive inert gas filter unit 3-2, and an iodine filter unit 3-3, which are interconnected in sequence. The dust and aerosol filter unit 3-1 is constructed from glass fiber, synthetic fiber, or aerogel to remove impurities such as dust and radioactive aerosols from the gas medium. The radioactive inert gas filter unit 3-2 is constructed from a nanoporous adsorbent material, preferably based on carbon, graphite, or graphene, to absorb radioactive inert gases produced by the reactor. The iodine filter unit 3-3 includes an iodine adsorber to remove radioactive iodine isotopes from the tritium-laden gas medium.

[0344] The tritium collection system 3-A also includes a gaseous medium cooling and tritium catalysis unit 3-4 and a gas-liquid separation and liquid tritium collection unit 3-5, which are interconnected. The gaseous medium cooling and tritium conversion / catalysis subsystem includes the gaseous medium cooling and tritium catalysis unit 3-4, while the tritium diversion subsystem includes the gas-liquid separation and liquid tritium collection unit 3-5. The gaseous medium cooling and tritium catalysis unit 3-4 is connected to the output of the tritium purification subsystem, preferably with its input connected to the output of the iodine filtration unit 3-3.

[0345] The output of the gas medium cooling and tritium catalysis unit 3-4 is connected to the gas-liquid separation and liquid tritium collection unit 3-5. This unit 3-4 includes a temperature control device that catalytically oxidizes tritium in the gas medium to produce tritiated water, then cools the gas medium. The cooled, condensed tritiated water flows into the gas-liquid separation and liquid tritium collection unit 3-5. By cooling the gas medium, the medium temperature is lowered to below 400°C, significantly reducing the diffusion and permeability of tritium. This controls tritium permeability, reduces tritium loss, and enhances radiation environmental friendliness. The gas medium cooling and tritium catalysis unit 3-4 is part of the gas cooling and tritium conversion / catalysis subsystem.

[0346] The gas-liquid separation and liquid tritium collection unit 3-5 includes a gas-liquid separator that separates tritiated water from a gaseous medium containing gaseous tritium. This unit, part of the tritium diversion subsystem, feeds the tritiated water and gaseous medium containing gaseous tritium into the tritium processing and storage system 3-B in two separate routes.

[0347] The tritium extraction subsystem 3-B1 includes a tritium physical state conversion unit 3-7; the tritium purification and separation subsystem 3-B2 includes a tritium separation and purification unit 3-8.

[0348] The tritium storage subsystem 3-B3 includes a liquid tritium storage unit 3-6 and a gaseous tritium storage unit 3-9.

[0349] Furthermore, the liquid tritium storage unit 3-6 and the tritium separation and purification unit 3-8 are both connected to the output end of the gas-liquid separation and liquid tritium collection unit 3-5, tritiated water enters the liquid tritium storage unit 3-6, and the gas medium and gaseous tritium enter the tritium separation and purification unit 3-8.

[0350] The tritium separation and purification unit 3-8 preferably has a centrifugal purification device to separate and purify the gaseous tritium in the gas medium. After separation and purification, the coolant and gas medium after tritium removal can be returned to the gas-cooled reactor for reuse, thereby improving economic efficiency.

[0351] Furthermore, as shown in Figure 10, in this embodiment, the tritium separation and purification unit 3-8 is connected to the gas-cooled reactor 1, allowing a portion of the gaseous medium in the gas-cooled reactor 1 to flow directly into the tritium separation and purification unit 3-8. The iodine filtration unit 3-3 can also be connected to the tritium separation and purification unit 3-8, allowing a portion of the gaseous medium purified by the tritium purification subsystem to flow directly into the tritium separation and purification unit 3-8. These features may not be implemented in other embodiments.

[0352] The tritium physical conversion unit 3-7 is located between the liquid tritium storage unit 3-6 and the tritium separation and purification unit 3-8. Tritiated water from the liquid tritium storage unit 3-6 flows into the tritium physical conversion unit 3-7. The tritium physical conversion unit 3-7 includes electrolysis equipment. Due to the different electrolysis rates of H and T (H-3) elements in the tritiated water, electrolysis technology is used to separate the tritium element from the tritiated water, forming gaseous tritium. The gaseous tritium-containing medium is then introduced into the tritium separation and purification unit 3-8. The gaseous tritium in the gaseous medium is also separated and purified through centrifugal purification equipment.

[0353] Furthermore, the gaseous tritium storage unit 3-9 is connected to the tritium separation and purification unit 3-8. The gaseous tritium storage unit 3-9 has a foam palladium or palladium matrix adsorber that can adsorb gaseous tritium for storage.

[0354] The gaseous tritium storage unit 3-9 is connected to the fuel pre-processing unit 3-15. The fuel pre-processing unit 3-15 includes physical parameter adjustment equipment to adjust the physical property parameters of the gaseous tritium and / or helium-3. After adjustment, the gas enters the tritium injection unit 3-16, which injects the tritium fuel and / or helium-3 fuel into the fusion reactor. The fuel pre-processing unit 3-15 also includes equipment for separating tritium and helium-3. After separation, the tritium fuel and helium-3 fuel enter the tritium injection unit 3-16 and are injected into the fusion reactor 2.

[0355] The above is the main process route of the tritium fuel supply system 3. Tritium is processed mainly by converting between liquid and gaseous states. This embodiment also provides a branch for solid-state storage of excess tritium produced by the gas-cooled reactor for further processing when needed.

[0356] Specifically, the tritium storage subsystem 3-B3 also includes a tritium liquid catalytic conversion unit 3-10, a tritium solidification unit 3-11, a solid tritium processing and storage unit 3-12, a tritium solidified material processing unit 3-13, and a tritium debinding unit 3-14, which are connected in sequence. The input end of the tritium liquid catalytic conversion unit 3-10 is connected to the gas tritium storage unit 3-9.

[0357] The tritium liquid catalytic conversion unit 3-10 preferably has an electric heater and a Laval atomizing nozzle, which converts excess gaseous tritium in the gaseous tritium storage unit 3-9 into liquid tritium and then atomizes it into nano-liquid particles at high temperature.

[0358] The tritium solidification unit 3-11 has a molecular reaction bed or a micromolecular reaction bed for catalytically solidifying nano-liquid particles and micro-nano magnesium particles to form tritiated magnesium powder particles (MgT2). The tritiated magnesium powder particles are processed into block products and stored in the solid tritium processing and storage unit 3-12.

[0359] When tritium needs to be extracted again, the tritium solidification product processing unit 3-13 is equipped with a crushing device to process the blocky magnesium tritide into tritide magnesium powder particles. The tritium debinding unit 3-14 preferably has a hydrolysis device to hydrolyze the tritide magnesium powder particles to form debound (solidified) gaseous or liquid tritium. The output end of the tritium debinding unit 3-14 is connected to the tritium physical state conversion unit 3-7.

[0360] The combined system of the present application can convert excess gaseous tritium stored in the gas tritium storage unit into solid blocks, so as to store the excess tritium produced by the gas-cooled reactor in a solid state, and then convert it into tritium fuel and / or helium-3 fuel for use when needed, thereby improving storage efficiency, facilitating long-term storage and transportation, and solving the problem of excess tritium produced by the gas-cooled reactor.

[0361] As can be seen, the tritium storage subsystem 3-B3 in this application includes one or more of a solid-state tritium processing and storage system, a liquid-state tritium processing and storage system, and a gaseous (free) tritium processing and storage system. Preferably, each system is interconnected to enable conversion of tritium into various physical states. The solid-state tritium processing and storage system includes a liquid-state tritium catalytic conversion unit 3-10, a tritium solidification unit 3-11, a solid-state tritium processing and storage unit 3-12, a tritium solidified material processing unit 9-13, and a tritium debinding unit 3-14.

[0362] The following describes the design of the gas-cooled reactor in this combined system:

[0363] As shown in FIG3 , the tritium production module system 204 includes a cladding 104 and a tritium production layer group. The cladding 104 is arranged at intervals along the radial direction of the gas-cooled reactor 1. The cladding 104 is located at the outermost layer of the tritium production module system along the radial direction of the reactor, and the tritium production layer group is located between two layers of cladding 104. The tritium production layer group includes at least one of a tritium breeder layer 106 and a tritium breeder multiplication layer. Both the tritium breeder layer 106 and the tritium breeder multiplication layer include a tritium production region, and the tritium production region includes tritium breeding material.

[0364] A neutron multiplying layer 105 may also be provided in the tritium-producing layer group. Neutron multiplying layer 105 comprises a neutron multiplying material. Neutron multiplying layer 105 may be provided together with either or both of tritium breeder layer 106 and tritium multiplier layer 106. Preferably, when only tritium breeder layer 106 is provided in the tritium-producing layer group, neutron multiplying layer 105 is also provided.

[0365] As shown in Figure 1, the tritium-producing layer group also includes a tritium pipe 101 for the circulation of reactor coolant and tritium-containing medium. The tritium pipe 101 extends along the axial direction of the gas-cooled reactor 1. A plurality of holes are opened on the wall of the tritium pipe 101, so that the interior of the tritium pipe 101 is fluidically connected to the tritium-producing area.

[0366] The tritium pipe 101 is a single-layer or multi-layer pipe. Preferably, the tritium pipe 101 is a two- to three-layer pipe, with holes provided on the wall of each layer. The number of holes increases layer by layer, and / or the size of the holes increases layer by layer, from the outer layer to the inner layer of the tritium pipe 101. This results in a gradually decreasing pressure and increasing airflow rate from the outer layer to the inner layer of the tritium pipe, thereby enhancing the release and diffusion efficiency of tritium from the tritium-producing region into the tritium pipe.

[0367] The tritium production module system 204 includes a coolant inlet, and the coolant inlet includes a second gas acceleration device 103. The tritium pipeline 101 is connected to the second gas acceleration device 103. The second gas acceleration device 103 has a structure with a changing cross-sectional area, which is not limited to a tubular structure with a changing cross-sectional area, or a plate-like structure, etc. It includes a contraction section, a narrow throat section and an expansion section connected in sequence along the direction of gas flow, and the cross-sectional area of ​​the contraction section changes from large to small along the flow direction, and the cross-sectional area of ​​the expansion section changes from small to large along the flow direction. Preferably, the second gas acceleration device 103 has a Laval nozzle designed using the Bernoulli principle and related physical principles, or a structure similar thereto. In addition, in other embodiments, the second gas acceleration device 103 may only include the contraction section therein, and may also play a role in accelerating the gas.

[0368] The second gas accelerator 103 significantly increases the flow rate of the gaseous medium entering the tritium pipeline. This increases the flow rate of the tritium-containing medium within the tritium production module system, allowing the flow rate, pressure, and density of the gaseous medium entering different structural layers of the tritium production module system to differ, thereby enhancing the gaseous medium's ability and efficiency to carry tritium. The ultrasonic vibrations generated simultaneously remove tritium deposited and adhering to the flow channel walls and within the tritium production module system, thereby reducing tritium sedimentation and adsorption losses. Furthermore, the second gas accelerator 103 interacts with the holes in the pipeline wall, increasing the gas flow rate and decreasing the pressure layer by layer from the outer to the inner layers of the tritium pipeline 101, further enhancing the efficiency of tritium release and diffusion into the pipeline.

[0369] As shown in Figures 1 and 3 , the tritium-producing layer group includes a neutron multiplying layer 105 and a tritium breeder layer 106 arranged radially along the gas-cooled reactor. The tritium breeder layer 106 is located outside the neutron multiplying layer 105 , and at least a portion of the tritium pipe 101 is located inside the tritium breeder layer 106 .

[0370] The tritium production module system 204 further includes partitions 109 . Partitions 109 are provided between different types of layers in the tritium production layer group, and partitions 109 may also be provided between the tritium production layer group and other layers.

[0371] The tritium production module system 204 also includes a tritium-proof layer, adjacent to the cladding 104. The layer is a coating or low-permeability structure. The layer comprises an oxide and a titanium-containing ceramic. The oxide comprises one or more of the following: Cr2O3, Al2O3, and Ti2O2. The titanium-containing ceramic is preferably titanium aluminum carbide. The layer effectively prevents tritium from penetrating outside the tritium production module system and causing loss.

[0372] The tritium production module system 204 also includes an irradiation product production layer 1011. The materials of the irradiation product production layer 1011 include one or more of the following substances: Np-237 and its compounds for producing Pu-238, and Co-59 and its compounds for producing Co-60; partitions 109 are arranged on both sides of the irradiation product production layer 1011, and the irradiation product production layer 1011 is located on the outside of the tritium breeding layer 106.

[0373] Tritium production module system 204 also includes a reflector layer 1010 or moderator layer, located outside of irradiated product production layer 1011. The reflector layer 1010 or moderator layer is made of one or more of the following materials: graphite, isostatically pressed graphite, nuclear-grade graphite, boron carbide, silicon carbide, boron-containing silicon carbide, beryllium oxide, or a beryllium-containing compound. The reflector layer reflects neutrons, improving neutron utilization and increasing tritium production.

[0374] In some other embodiments, the irradiated product production layer 1011 may also be placed between any two layers of the neutron multiplication layer, tritium breeding layer, tritium breeding multiplication layer, moderation layer or reflection layer, and partitions are provided between the irradiated product production layer and other layers.

[0375] As shown in Figure 3, the tritium production module system 204 is preferably cylindrical in shape, completely surrounding the reactor core. The tritium production module system 204 is circumferentially composed of multiple tritium production submodules, with partitions 109 positioned between adjacent modules. Preferably, the number of tritium production submodules ranges from 4 to 24. Specifically, the tritium production submodules are cylindrical in shape, with a sector cross-section angle of 15° to 90°.

[0376] Furthermore, the gas-cooled reactor 1 includes a core 1014, a nuclear fuel containment barrier 1016, and a reactor pressure vessel 1017, which are arranged radially from the inside to the outside of the gas-cooled reactor. The tritium production module system 204 is located outside the core 1014 and between the nuclear fuel containment barrier 1016 and the reactor pressure vessel 1017. The nuclear fuel containment barrier 1016 includes a metal container or enclosure and also includes fixed support members.

[0377] In addition, a neutron regulation layer 1015 is provided between the core 1014 and the nuclear fuel sealing isolation layer 1016. The neutron regulation layer 1015 includes a coolant flow channel, and / or a neutron multiplication layer and / or a reflection layer and / or a moderation layer.

[0378] In a gas-cooled reactor, by setting up a tritium production module system outside the core to produce tritium, the radiation hazard of neutron leakage from the high core of the gas-cooled reactor to reactor components and external personnel and equipment can be solved, and the thickness of the reflector layer, moderator layer and external shielding body in the gas-cooled reactor can be reduced.

[0379] As shown in FIG6 , the gas-cooled reactor includes a reactor coolant inlet, at which a first gas acceleration device 206 is provided. A gas medium physical parameter adjustment system is provided on the first gas acceleration device 206 . The first gas acceleration device 206 has a similar structure to the second gas acceleration device 103 .

[0380] The gas medium physical parameter adjustment system includes multiple connecting pipes and valve assemblies. A plurality of holes are opened on the wall surface of the air inlet section of the first gas acceleration device 206, which are respectively connected to the multiple connecting pipes. The valve assemblies are arranged on the multiple connecting pipes. The valve assemblies include but are not limited to one or more of a regulating valve, a constant pressure check valve and a variable pressure check valve.

[0381] In the gas-cooled reactor 1, by setting a first gas acceleration device at the reactor coolant inlet, the flow rate of the gas medium in the gas-cooled reactor can be increased, thereby enhancing the circulation speed and efficiency of the gas medium; by setting a gas medium physical parameter adjustment system, the pressure and flow rate and other parameters of the gas medium in the air inlet section of the first gas acceleration device 206 can be adjusted and changed according to different operating conditions of the reactor, such as different operating powers, thereby achieving automatic adjustment of the reactor cooling efficiency and tritium loading efficiency.

[0382] The reactor coolant inlet is connected to the core 1014 and the tritium production module system 204 respectively. The gas-cooled reactor also includes a diverter plate 207. The diverter plate 207 is located between the first gas acceleration device 206 and the core 1014, and also between the first gas acceleration device 206 and the tritium production module system 204. The gas-cooled reactor is provided with a diverter plate to isolate the gas coolant entering the core from the gas medium entering the tritium production module system, so that the high-tritium gas medium will not be mixed into the core coolant after entering the tritium production module system, and the tritium radioactivity level of the gas medium in the core coolant system is maintained.

[0383] In addition, the gas parameters of the reactor coolant entering the core 1014 and the tritium production module system 204 can be adjusted separately through the diverter plate 207.

[0384] Preferably, the diverter plate 207 is connected to the first gas accelerator 206, and the airflow rate can be controlled by adjusting the size of the opening at the junction of the diverter plate 207 and the first gas accelerator 206. Subsequently, based on the parameter range of the gas medium after passing through the first gas accelerator 206, the volume of the space between the diverter plate 207 and the reactor pressure vessel 1017, and other parameters, can be adjusted to further adjust the amount and parameters of the coolant entering the core 1014 and the tritium production module system 204, respectively. By sequentially adjusting the gas parameters through the first gas accelerator 206 and the diverter plate 207, the reactor coolant entering the tritium production module system 204 can be coupled to the second gas accelerator 103, thereby enhancing the tritium-carrying capacity of the gas medium in the tritium production module system.

[0385] In summary, from the above description, it can be seen that the above-mentioned embodiment 8 of the present invention achieves the following technical effects:

[0386] 1. The combined system of the present application provides a tritium supply system and designs the specific composition and structure of the tritium supply system. The tritium produced by the gas-cooled reactor is collected, processed, stored, and transported in the tritium supply system to obtain tritium fuel and / or helium-3 fuel, which is then provided to the fusion reactor to solve the problems of tritium self-sustaining and fuel replenishment in the fusion reactor. 2. The combined system of the present application provides a two-way fission fuel supply system, allowing the gas-cooled reactor and fusion reactor within the combined system to provide nuclear fuel to each other, achieving the goal of joint symbiosis of gas-cooled reactors and fusion reactors, increasing the utilization rate of fission fuel, reducing total radioactive waste, enhancing the economic efficiency of the combined system, and improving environmental friendliness. 3. The combined system of the present application can convert the excess gaseous tritium stored in the gas tritium storage unit into solid blocks to store the excess tritium produced by the gas-cooled reactor in a solid state, and then convert it into tritium fuel and / or helium-3 fuel for use when needed, thereby improving storage efficiency, facilitating long-term storage and transportation, and solving the problem of excess tritium produced by the gas-cooled reactor. 4. The combined system of the present application connects the tritium production module system and the core of the gas-cooled reactor by setting the input of the tritium collection system to be connected. When there is no need to extract or purify the core coolant for tritium, only the connection between the tritium production module system and the tritium collection system can be opened, and the reactor coolant after separation and purification to remove tritium can be returned to the gas-cooled reactor for reuse, thereby improving economic efficiency.

[0387] The foregoing description is merely a preferred embodiment of the present invention and is not intended to limit the present invention. Those skilled in the art will readily appreciate that various modifications and variations of the present invention are possible. Any modifications, equivalent substitutions, or improvements made within the spirit and principles of the present invention are intended to be within the scope of protection of the present invention.

Claims

1. A tritium production module system is arranged inside a reactor, the tritium production module system has a multi-layer structure distributed along the radial direction of the reactor, the tritium production module system comprises a tritium production area and a circulation area, the tritium production area comprises tritium breeding materials, and the tritium breeding materials react with neutrons to produce tritium elements; The tritium producing module system is in fluid communication with an exterior of the tritium producing module system through the flow-through region; Features: The circulation area includes a tritium pipeline, the tritium pipeline is used for the circulation of reactor coolant and tritium-containing medium, and the tritium pipeline extends along the axial direction of the reactor; A plurality of holes are opened on the wall of the tritium pipeline, and the tritium pipeline is fluidically connected with the tritium producing area through the holes.

2. The tritium production module system according to claim 1, characterized in that: The tritium pipeline is a multi-layer pipeline, and a plurality of holes are opened on the pipe wall of any layer of the multi-layer pipeline or any multi-layer pipeline.

3. The tritium production module system according to claim 2, characterized in that: The tritium pipeline is a 2-3 layer pipeline and the holes are arranged on the pipe wall of each layer of the pipeline. From the outer layer to the inner layer of the tritium pipeline, the number of the holes increases layer by layer.

4. The tritium production module system according to any one of claims 1 to 3, characterized in that: The tritium production module system includes a coolant inlet, and the coolant inlet includes a fluid acceleration device, and the fluid acceleration device is connected to the tritium pipeline.

5. The tritium production module system according to claim 4, characterized in that: The fluid acceleration device is a structure with a changing cross-sectional area, and includes a contraction section, or a contraction section, a narrow throat section and an expansion section connected in sequence along the flow direction. The cross-sectional area of ​​the contraction section changes from large to small along the flow direction, and the cross-sectional area of ​​the expansion section changes from small to large along the flow direction.

6. The tritium production module system according to claim 5, characterized in that: The tritium production module system also includes a cladding and a tritium production layer group, wherein the cladding is arranged at intervals along the radial direction of the reactor, the tritium production layer group is located between the claddings, the tritium production layer group includes a tritium breeding layer and / or a tritium breeding multiplication layer, and the tritium pipeline is at least partially located in the tritium production layer group.

7. The tritium production module system according to claim 6, characterized in that: The tritium producing layer group comprises a neutron multiplying layer and a tritium breeding layer which are arranged along the radial direction of the reactor. The tritium breeding layer is located outside the neutron multiplying layer, and the tritium pipeline is at least partially located inside the tritium breeding layer.

8. The tritium production module system according to claim 7, characterized in that: The tritium production module system also includes a partition, which is located between different types of layers in the tritium production layer group; the tritium production module system also includes an anti-tritium penetration layer, which is adjacent to the cladding and adopts a coating or a low-permeability structure. The anti-tritium penetration layer includes oxides and titanium-containing ceramics, and the oxides include one or more of the following substances: Cr2O3, Al2O3, Ti2O2.

9. The tritium production module system according to claim 8, characterized in that: The tritium production module system also includes a reflection layer or a moderator layer, and the material of the reflection layer or the moderator layer includes one or more of the following substances: graphite, isostatic graphite, nuclear-grade graphite, boron carbide, silicon carbide, boron-containing silicon carbide, beryllium oxide or beryllium-containing compounds.

10. The tritium production module system according to claim 9, characterized in that: The tritium production module system also includes an irradiation product production layer, the material of which includes one or more of the following substances: Np-237 and its compounds for producing Pu-238, Co-59 and its compounds for producing Co-60, and the partitions are arranged on both sides of the irradiation product production layer.

11. The tritium production module system according to claim 10, characterized in that: The tritium production module system includes the cladding, the anti-tritium penetration layer, the neutron multiplication layer, the partition, the tritium breeding layer, the partition, the irradiation product production layer, the partition, the reflection layer or the moderation layer, the anti-tritium penetration layer, and the cladding, which are arranged in sequence from the inside to the outside along the radial direction of the reactor.

12. The tritium production module system according to claim 7, characterized in that: The tritium-producing layer group includes a first circulation structure, in which the neutron multiplication layer and the tritium breeding layer arranged along the radial direction of the reactor circulate multiple times; Alternatively, the tritium producing layer group includes a second circulation structure, in which any arrangement and combination of the neutron multiplying layer, the tritium breeding layer and the tritium breeding multiplying layer arranged along the radial direction of the reactor circulates multiple times.

13. The tritium production module system according to claim 6, characterized in that: The tritium-producing layer group includes a tritium proliferation multiplication layer, and the tritium proliferation multiplication layer includes a neutron multiplication section and a cylindrical tritium proliferation section. A plurality of tritium proliferation sections are evenly arranged in the neutron multiplication section, and a volume ratio of the neutron multiplication section to the tritium proliferation section is in the range of 2:1 to 8:

1. The tritium pipes are arranged in an array in the tritium proliferation section.

14. The tritium production module system according to any one of claims 6 to 13, characterized in that: The tritium production module system is in the shape of a circular column and completely surrounds the periphery of the core of the reactor in the circumferential direction. The tritium production module system is composed of a plurality of tritium production sub-modules spliced ​​together in the circumferential direction, and the number of the tritium production sub-modules is in the range of 4 to 24.

15. The tritium production module system according to any one of claims 7 to 12, characterized in that: The neutron multiplying layer comprises a neutron multiplying material ball, wherein the neutron multiplying material ball contains a neutron multiplying material, and the neutron multiplying material comprises beryllium and a beryllium-containing compound; The tritium breeding layer comprises a tritium breeding material ball, wherein the tritium breeding material ball contains the tritium breeding material, and the tritium breeding material comprises one or a mixture of several of the following substances: Li2O, Li2TiO3, LiAlO2, Li4SiO4, and Li2ZrO3 ceramics.

16. The tritium production module system according to claim 15, characterized in that: The tritium breeding multiplication layer includes the neutron multiplication material ball and the tritium breeding material ball; Or the tritium breeding multiplication layer comprises a tritium breeding multiplication material sphere, the core part of the tritium breeding multiplication material sphere comprises the tritium breeding material, and the shell part of the tritium breeding multiplication material sphere comprises the neutron multiplication material.

17. The tritium production module system according to claim 14, characterized in that: The enrichment of Li-6 in the tritium breeder material is 7.5%-90%, the enrichment of Li-7 is 10%-92.5%, and the enrichment of Li-6 and Li-7 is 100% in total; the tritium breeder material with a Li-7 enrichment of 50%-92.5% is arranged at a position close to the core, and the tritium breeder material with a Li-6 enrichment of 50%-90% is arranged at a position far away from the core.

18. The tritium production module system according to any one of claims 7 to 12, characterized in that: The neutron multiplication layer, the tritium proliferation layer and the tritium proliferation multiplication layer all include a tritium production layer group air inlet, and the tritium production layer group air inlet is provided with a support structure and a first filter screen for preventing the material in the tritium production layer group from leaking out.

19. The tritium production module system according to claim 18, characterized in that: A second filter screen or filter membrane is arranged inside or outside the wall of the tritium pipeline to prevent materials or dust in the tritium-producing layer group from entering the tritium pipeline.

20. A gas-cooled reactor, characterized in that: It comprises a tritium production module system according to any one of claims 1 to 19, wherein the tritium production module system is arranged at the periphery of the core of the gas-cooled reactor, and the tritium production module system reacts with neutrons in the core to produce tritium elements.

21. The gas-cooled reactor according to claim 20, characterized in that: The gas-cooled reactor comprises a core, a nuclear fuel sealing isolation layer and a reactor pressure vessel which are arranged radially from inside to outside, and the tritium production module system is located between the nuclear fuel sealing isolation layer and the reactor pressure vessel.

22. The gas-cooled reactor according to claim 21, characterized in that: The nuclear fuel sealing isolation layer includes a metal container or a shroud, and also includes a fixed supporting member.

23. The gas-cooled reactor according to claim 21, characterized in that: The gas-cooled reactor further includes a neutron regulating layer, which includes a first neutron regulating layer, a second neutron regulating layer and a third neutron regulating layer, and the neutron regulating layer includes a coolant flow channel and / or a neutron multiplication layer and / or a reflection layer and / or a moderator layer.

24. The gas-cooled reactor according to claim 23, characterized in that: The second neutron regulating layer is arranged between the nuclear fuel sealing isolation layer and the tritium production module system.

25. The gas-cooled reactor according to claim 23, characterized in that: The third neutron regulating layer is arranged between the reactor pressure vessel and the tritium production module system.

26. The gas-cooled reactor according to claim 23, characterized in that: The first neutron regulating layer is arranged between the core and the nuclear fuel sealing isolation layer.

27. A tritium system, characterized in that: It comprises a tritium production module system according to any one of claims 1 to 19, and also comprises a tritium fuel supply system, wherein the tritium production module system is connected to the tritium fuel supply system, the reactor coolant and tritium-containing medium in the tritium production module system are input into the tritium fuel supply system to obtain tritium and / or helium-3 fuel, and the tritium fuel and / or the helium-3 fuel are transported to a fusion reactor.

28. The tritium system of claim 27, wherein: The tritium fuel supply system includes a tritium collection system, a tritium processing and storage system, and a tritium replenishment system which are connected in sequence. The tritium collection system is connected to the tritium production module system, and the tritium replenishment system is connected to the fusion reactor.

29. The tritium system according to claim 28, characterized in that: The tritium processing and storage system includes: a tritium extraction system, a tritium purification and separation system, a tritium storage system and a tritium monitoring system. The tritium monitoring system is respectively associated with the tritium extraction system, the tritium purification and separation system and the tritium storage system to monitor the equipment and facilities of each system.

30. The tritium system of claim 28, wherein: The tritium collection system includes: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion / catalysis system.

31. The tritium system of claim 28, wherein: The tritium replenishment system includes: a feed pretreatment system and a tritium injection system.

32. A gas-cooled reactor, comprising a core, a nuclear fuel sealing isolation layer and a reactor pressure vessel arranged from inside to outside along the radial direction of the gas-cooled reactor, characterized in that: It also includes a tritium production module system, which is located at the periphery of the core and between the nuclear fuel sealing isolation layer and the reactor pressure vessel. The tritium production module system includes tritium breeding materials, and the tritium breeding materials react with neutrons generated by the core to produce tritium elements.

33. The gas-cooled reactor according to claim 32, characterized in that: The gas-cooled reactor comprises a reactor coolant inlet, a first gas acceleration device is arranged at the reactor coolant inlet, and a gas medium physical parameter adjustment system is arranged on the first gas acceleration device.

34. The gas-cooled reactor according to claim 33, characterized in that: The gas medium physical parameter adjustment system includes multiple connecting pipes and valve assemblies. A plurality of holes are opened on the wall surface of the air inlet section of the first gas acceleration device, which are respectively connected to the multiple connecting pipes. The valve assembly is arranged on the multiple connecting pipes, and the valve assembly includes a regulating valve, a constant pressure check valve and / or a variable pressure check valve.

35. The gas-cooled reactor according to claim 34, characterized in that: The reactor coolant inlet is connected to the core and the tritium production module system respectively. The gas-cooled reactor includes a diverter plate, which is located between the first gas acceleration device and the core, and also between the first gas acceleration device and the tritium production module system. The diverter plate isolates the reactor coolant entering the core from the reactor coolant entering the tritium production module system.

36. The gas-cooled reactor according to claim 35, characterized in that: The tritium production module system comprises a tritium production module system coolant inlet, and the tritium production module system coolant inlet is provided with a second gas acceleration device; By adjusting the space between the diverter plate and the reactor pressure vessel, the gas intake amount and parameters of the reactor coolant entering the second gas acceleration device are adjusted, and the reactor coolant entering the tritium production module system is coupled to the second gas acceleration device.

37. The gas-cooled reactor according to claim 36, characterized in that: The first gas acceleration device and / or the second gas acceleration device has a cross-sectional area variation structure, including a contraction section, or a contraction section, a narrow throat section and an expansion section sequentially connected along the gas flow direction, wherein the cross-sectional area of ​​the contraction section changes from large to small along the flow direction, and the cross-sectional area of ​​the expansion section changes from small to large along the flow direction.

38. The gas-cooled reactor according to any one of claims 32 to 37, characterized in that: The tritium producing module system also includes a cladding and a tritium producing layer group, wherein the cladding is arranged at intervals along the radial direction of the gas-cooled reactor, and the tritium producing layer group is located between the claddings, and the tritium producing layer group includes a tritium breeding layer and / or a tritium breeding multiplication layer, and the tritium breeding layer and the tritium breeding multiplication layer both include a tritium producing region, and the tritium producing region includes the tritium breeding material.

39. The gas-cooled reactor according to claim 38, characterized in that: The tritium-producing layer group also includes a tritium pipeline for the circulation of the reactor coolant and the tritium-containing medium. The tritium pipeline extends along the axial direction of the gas-cooled reactor. A plurality of holes are opened on the wall of the tritium pipeline so that the inside of the tritium pipeline is fluidically connected with the tritium-producing region.

40. The gas-cooled reactor according to claim 39, characterized in that: The tritium producing layer group includes a first neutron multiplying layer and a tritium breeding layer arranged radially along the gas-cooled reactor, the tritium breeding layer is located outside the first neutron multiplying layer, the first neutron multiplying layer includes a neutron multiplying material, and the tritium pipeline is at least partially located in the tritium breeding layer.

41. The gas-cooled reactor according to claim 40, characterized in that: The tritium-producing module system also includes a partition, which is arranged between different types of layers in the tritium-producing layer group and / or between the tritium-producing layer group and other layers; the tritium-producing module system also includes an anti-tritium permeation layer, which is adjacent to the cladding, and the anti-tritium permeation layer includes oxides and titanium-containing ceramics, and the oxides include one or more of the following substances: Cr2O3, Al2O3, Ti2O2.

42. The gas-cooled reactor according to claim 41, characterized in that: The tritium production module system also includes an irradiation product production layer, and the material of the irradiation product production layer includes one or more of the following substances: Np-237 and its compounds for producing Pu-238, Co-59 and its compounds for producing Co-60; the partitions are arranged on both sides of the irradiation product production layer, and the irradiation product production layer is located on the outside of the tritium breeding layer.

43. The gas-cooled reactor according to claim 42, characterized in that: The tritium production module system also includes a first reflection layer or a first moderator layer, which is located on the outside of the irradiation product production layer. The material of the first reflection layer or the first moderator layer includes one or more of the following substances: graphite, isostatic graphite, nuclear-grade graphite, boron carbide, silicon carbide, boron-containing silicon carbide, beryllium oxide or beryllium-containing compounds.

44. The gas-cooled reactor according to claim 39, characterized in that: The tritium-producing layer group includes a tritium proliferation multiplication layer, and the tritium proliferation multiplication layer includes a neutron multiplication section and a cylindrical tritium proliferation section. A plurality of tritium proliferation sections are evenly arranged in the neutron multiplication section, and a volume ratio of the neutron multiplication section to the tritium proliferation section is in the range of 2:1 to 8:

1. The tritium pipes are arranged in an array in the tritium proliferation section.

45. The gas-cooled reactor according to claim 37, characterized in that: The core includes a fuel assembly. Along the axial direction of the gas-cooled reactor, the fuel assembly is divided into multiple sections. From the air inlet end to the air outlet end of the fuel assembly, the fissile nuclide enrichment of the fuel assembly increases section by section.

46. ​​The gas-cooled reactor according to claim 45, characterized in that: The fuel assembly is divided into 3 to 8 sections along the axial direction of the gas-cooled reactor, and the multiple sections of the fuel assembly use 3 to 4 kinds of fuels with fissile nuclides of different enrichment degrees.

47. The gas-cooled reactor according to claim 46, characterized in that: The fuel assembly includes a fuel assembly coolant flow channel, and a third gas acceleration device is arranged on the fuel assembly coolant flow channel. The third gas acceleration device adopts a structure with a changing cross-sectional area, including the contraction section, or the contraction section, the narrow throat section and the expansion section connected in sequence along the gas flow direction.

48. The gas-cooled reactor according to claim 47, characterized in that: The fuel assembly is cylindrical as a whole and is divided into multiple layers along the radial direction of the gas-cooled stack. The coolant flow channel of the fuel assembly includes an interlayer flow channel, and the interlayer flow channel is a gap of 2mm to 20mm between different layers of the fuel assemblies; the fuel assembly is also divided into multiple sectors along the circumferential direction of the gas-cooled stack, so that each layer of the fuel assembly has multiple fuel elements. The coolant flow channel of the fuel assembly also includes an axial channel, and each fuel element has a plurality of the axial channels along the axial direction of the gas-cooled stack.

49. The gas-cooled reactor according to claim 48, characterized in that: The number of axial holes on each fuel element is determined according to the following formula: Wherein n is the number of the axial holes, θ is the central angle of the sector where the fuel element is located, and m is the number of layers where the fuel element is located along the radial direction from inside to outside of the gas-cooled reactor.

50. The gas-cooled reactor according to any one of claims 45 to 49, characterized in that: The gas-cooled reactor is a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor, and the thermal neutron injection rate of the tritium production module system of the high-flux gas-cooled reactor is 1.0×10 11 ~5.0×10 15 n / cm 2 ·s, and the fast neutron injection rate is 1.5×10 10 ~1.0×10 15 n / cm 2 ·s; the thermal neutron injection rate of the tritium production module system of the high-flux gas-cooled fast reactor is 1.0×10 11 ~5.0×10 15 n / cm 2 ·s, and the fast neutron injection rate is 3×10 12 ~5.0×10 15 n / cm 2 ·s.

51. The gas-cooled reactor according to claim 50, characterized in that: The high-flux gas-cooled reactor and the high-flux gas-cooled fast reactor use uranium fuel or uranium-thorium MOX fuel, wherein the enrichment of U-235 is not less than 15%; if uranium-plutonium MOX fuel, thorium-plutonium MOX fuel or uranium-thorium-plutonium MOX fuel is used, the enrichment of Pu-239 is not less than 10%.

52. The gas-cooled reactor according to any one of claims 39 to 44, characterized in that: A coolant flow channel and / or a second neutron multiplication layer and / or a second reflection layer and / or a second moderator layer are arranged between the nuclear fuel sealing isolation layer and the tritium production module system; the coolant flow channel and / or a third neutron multiplication layer and / or a third reflection layer and / or a third moderator layer are arranged between the reactor pressure vessel and the tritium production module system.

53. The gas-cooled reactor according to claim 52, characterized in that: The nuclear fuel sealing isolation layer includes a metal container or a shroud, and also includes a fixed support member. A neutron regulating layer is arranged between the core and the nuclear fuel sealing isolation layer, and the neutron regulating layer includes the coolant flow channel and / or the fourth neutron multiplication layer and / or the fourth reflection layer and / or the fourth moderation layer.

54. The gas-cooled reactor according to claim 53, characterized in that: The thermal neutron injection rate of the tritium production module system of the gas-cooled reactor is 1.0×10 10 ~2.0×10 13 n / cm 2 ·s, and the fast neutron injection rate is 5.0×10 9 ~5.0×10 12 n / cm 2 ·s; if the gas-cooled reactor is a gas-cooled fast reactor, the thermal neutron injection rate of the tritium production module system is 1.0×10 10 ~2.0×10 13 n / cm 2 ·s, and the fast neutron injection rate is 5.0×10 9 ~1.0×10 13 n / cm 2 ·s.

55. The gas-cooled reactor according to claim 51, characterized in that: The gas-cooled reactor and the gas-cooled fast reactor use the uranium fuel or the uranium-thorium MOX fuel, wherein the enrichment of U-235 is not less than 4.5%; if the uranium-plutonium MOX fuel, the thorium-plutonium MOX fuel or the uranium-thorium-plutonium MOX fuel is used, the enrichment of Pu-239 is not less than 5%.

56. A combined system of a gas-cooled reactor and a fusion reactor, characterized in that: The combined system comprises the fusion reactor and the gas-cooled reactor according to any one of claims 32-55, wherein the fusion reactor comprises various fusion reactors using tritium and / or helium-3 as fusion fuel and fusion-fission hybrid reactors; the combined system further comprises a tritium supply system, wherein the tritium supply system is connected to the gas-cooled reactor and also to the fusion reactor, the gas-cooled reactor produces tritium, and the tritium fuel and / or helium-3 fuel is provided to the fusion reactor through the tritium supply system.

57. The combined system according to claim 56, characterized in that: The tritium supply system includes a tritium collection system, a tritium processing and storage system, and a tritium fuel replenishment system which are connected in sequence. The tritium collection system is connected to the gas-cooled reactor, and the tritium fuel replenishment system is connected to the fusion reactor.

58. The combined system according to claim 57, characterized in that: The tritium processing and storage system includes: a tritium extraction system, a tritium purification and separation system, a tritium storage system and a tritium monitoring system; the tritium monitoring system is associated with the tritium extraction system, the tritium purification and separation system and the tritium storage system, and monitors the equipment and facilities in each system.

59. The combined system according to claim 58, characterized in that: The tritium collection system includes: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion / catalysis system; the tritium fuel replenishment system includes: a feed pretreatment system and a tritium injection system.

60. The combined system of claim 57, wherein: The input of the tritium collection system is in communication with the tritium production module system of the gas-cooled reactor, and the reactor coolant and tritium-containing medium in the tritium production module system enter the tritium supply system.

61. The combined system according to claim 60, characterized in that: The input of the tritium collection system is connected to the core of the gas-cooled reactor, and the reactor coolant in the core enters the tritium supply system. After separation and purification to remove tritium, the reactor coolant returns to the gas-cooled reactor for reuse.

62. The combined system of claim 56, wherein: The combined system also includes a fission fuel bidirectional supply system, including a first nuclear fuel supply system and a second nuclear fuel supply system. The gas-cooled reactor provides one or more of the following substances to the fusion reactor through the first nuclear fuel supply system: depleted uranium, Th-232, U-238 and Pu-239 initial fuel.

63. The combined system according to claim 62, characterized in that: The fusion reactor provides Pu-239 and / or U-233 to the gas-cooled reactor through the second nuclear fuel supply system.

64. A combined system of a gas-cooled reactor and a fusion reactor, characterized in that: comprising the gas-cooled reactor and the fusion reactor; a tritium fuel supply system connected to both the gas-cooled reactor and the fusion reactor, wherein the gas-cooled reactor generates tritium and passes a coolant and a gas medium containing the tritium into the tritium fuel supply system to obtain tritium and / or helium-3 fuel, and the tritium fuel and / or the helium-3 fuel are transported to the fusion reactor; A fission fuel two-way supply system is connected to both the gas-cooled reactor and the fusion reactor, and the gas-cooled reactor and the fusion reactor provide nuclear fuel to each other through the fission fuel two-way supply system; The fusion reactor includes various fusion reactors or fusion-fission hybrid reactors using tritium and / or helium-3 as fusion fuel.

65. The combined system of claim 64, characterized in that: The tritium fuel supply system includes a tritium collection system, a tritium processing and storage system, and a tritium replenishment system which are connected in sequence. The tritium collection system is connected to the gas-cooled reactor, and the tritium replenishment system is connected to the fusion reactor.

66. The combined system of claim 65, characterized in that: The tritium processing and storage system includes: a tritium extraction subsystem, a tritium purification and separation subsystem, a tritium storage subsystem and a tritium monitoring subsystem; the tritium monitoring subsystem is associated with the tritium extraction subsystem, the tritium purification and separation subsystem and the tritium storage subsystem, and monitors the equipment and facilities of each subsystem.

67. The combined system of claim 66, characterized in that: The tritium collection system includes: a tritium purification subsystem, a tritium diversion subsystem, a gas cooling and tritium conversion / catalysis subsystem, and the tritium purification subsystem is connected to the gas-cooled reactor.

68. The combined system according to claim 67, characterized in that: The tritium replenishment system includes a feed pretreatment unit and a tritium injection unit, and the tritium injection unit is connected to the fusion reactor.

69. The combined system according to any one of claims 65 to 68, characterized in that: The fission fuel bidirectional supply system includes a first nuclear fuel and isotope reprocessing system connected to both the gas-cooled reactor and the fusion reactor. Through the first nuclear fuel and isotope reprocessing system, the gas-cooled reactor provides one or more of the following substances to the fusion reactor: depleted uranium, Th-232, U-238, and Pu-239 initial fuel.

70. The combined system of claim 69, characterized in that: The fission fuel bidirectional supply system also includes a second nuclear fuel and isotope reprocessing system connected to both the gas-cooled reactor and the fusion reactor. Through the second nuclear fuel and isotope reprocessing system, the fusion reactor provides Pu-239 and / or U-233 to the gas-cooled reactor.

71. The combined system according to claim 70, characterized in that: The first nuclear fuel and isotope reprocessing system includes a spent fuel receiving and dissolving unit, a spent fuel and isotope separation and purification unit, a nuclide extraction unit, and a fusion reactor nuclear fuel manufacturing unit which are connected in sequence. The spent fuel receiving and dissolving unit is connected to the gas-cooled reactor, and the fusion reactor nuclear fuel manufacturing unit is connected to the fusion reactor.

72. The combined system according to claim 71, characterized in that: The second nuclear fuel and isotope reprocessing system includes a nuclear fuel cladding receiving and disintegration unit, a cladding shearing and decomposition unit, a nuclide separation and purification unit, and a gas-cooled reactor nuclear fuel manufacturing unit which are connected in sequence. The nuclear fuel cladding receiving and disintegration unit is connected to the fusion reactor, and the gas-cooled reactor nuclear fuel manufacturing unit is connected to the gas-cooled reactor.

73. The combined system of claim 72, characterized in that: The first nuclear fuel and isotope reprocessing system and the second nuclear fuel and isotope reprocessing system both include a radioactive waste treatment and storage unit and a tritium enrichment unit. The high-tritium-containing waste liquid and waste gas generated by the radioactive waste treatment and storage unit, and the tritium-containing material in the tritium enrichment unit are transported to the tritium collection system and / or the tritium treatment and storage system.

74. The combined system of claim 68, wherein: The gas-cooled reactor comprises a tritium production module system and a core. The tritium production module system is arranged at the periphery of the core. The tritium production module system comprises tritium breeding materials, which react with neutrons of the core to produce tritium elements.

75. The combined system of claim 74, characterized in that: The input end of the tritium purification subsystem is in communication with the tritium production module system, or the input end of the tritium purification subsystem is in communication with the tritium production module system and the core, respectively.

76. The combined system of claim 75, characterized in that: The tritium purification subsystem comprises a dust aerosol filter unit, a radioactive inert gas filter unit and an iodine filter unit which are connected in sequence. The dust aerosol filter unit comprises glass fiber, chemical fiber or aerogel, the radioactive inert gas filter unit comprises nanoporous adsorption material based on carbon, graphite or graphene, and the iodine filter unit comprises an iodine adsorber for removing radioactive iodine isotopes in the tritium-carrying gas medium.

77. The combined system of claim 76, characterized in that: The gas cooling and tritium conversion / catalysis subsystem includes a gas medium cooling and tritium catalysis unit, and the tritium diversion subsystem includes a gas-liquid separation and liquid tritium collection unit. The gas medium cooling and tritium catalysis unit has a temperature regulating device and is connected to the output end of the tritium purification subsystem. The output end of the gas medium cooling and tritium catalysis unit is connected to the gas-liquid separation and liquid tritium collection unit to catalytically oxidize the tritium in the gas medium into tritiated water and cool the gas medium. The gas-liquid separation and liquid tritium collection unit has a gas-liquid separator to separate the tritiated water and the gas medium containing gaseous tritium.

78. The combined system of claim 77, characterized in that: The tritium extraction subsystem includes a tritium physical state conversion unit; the tritium purification and separation subsystem includes a tritium separation and purification unit.

79. The combined system of claim 78, characterized in that: The tritium storage subsystem includes a liquid tritium storage unit and a gas tritium storage unit.

80. The combined system of claim 79, wherein: The liquid tritium storage unit and the tritium separation and purification unit are both connected to the output end of the gas-liquid separation and liquid tritium collection unit, the tritiated water enters the liquid tritium storage unit, the gas medium and the gaseous tritium enter the tritium separation and purification unit, and the tritium separation and purification unit has a centrifugal purification device to separate and purify the gaseous tritium in the gas medium.

81. The combined system of claim 80, characterized in that: The tritium separation and purification unit is connected to the gas-cooled reactor, part of the gas medium in the gas-cooled reactor directly enters the tritium separation and purification unit, and the gas medium after separation and purification to remove tritium enters the coolant system of the gas-cooled reactor for reuse.

82. The combined system of claim 81, characterized in that: The tritium physical state conversion unit is located between the liquid tritium storage unit and the tritium separation and purification unit. The tritium physical state conversion unit includes an electrolysis device, which ionizes and decomposes the tritiated water in the liquid tritium storage unit to form the gaseous tritium, and introduces the gas medium containing the gaseous tritium into the tritium separation and purification unit.

83. The combined system of claim 82, characterized in that: The gas tritium storage unit is in communication with the tritium separation and purification unit. The gas tritium storage unit has a foam palladium or palladium matrix adsorber for adsorbing the gaseous tritium for storage.

84. The combined system of claim 83, characterized in that: The gas tritium storage unit is connected to the fuel pretreatment unit, and the fuel pretreatment unit has a physical parameter adjustment device to adjust the physical characteristic parameters of the gaseous tritium and / or helium-3; the fuel pretreatment unit also includes a device for separating tritium and helium-3, which provides the tritium fuel and the helium-3 fuel to the fusion reactor respectively after separation.

85. The combined system of claim 84, characterized in that: The tritium storage subsystem also includes a tritium liquid catalytic conversion unit, a tritium solidification unit, a solid tritium processing and storage unit, a tritium solidification product processing unit, and a tritium debinding unit which are connected in sequence. The input end of the tritium liquid catalytic conversion unit is connected to the gas tritium storage unit.

86. The combined system of claim 85, characterized in that: The tritium liquid catalytic conversion unit has an electric heater and a Laval atomizing nozzle, which converts the excess gaseous tritium in the gaseous tritium storage unit into liquid tritium and then atomizes it into nano liquid particles.

87. The combined system of claim 86, characterized in that: The tritium solidification unit has a molecular reaction bed or a micromolecular reaction bed, which catalytically solidifies the nano liquid particles and micro-nano magnesium particles to form tritiated magnesium powder particles. The tritiated magnesium powder particles are processed into blocks and stored in the solid tritium processing and storage unit.

88. The combined system of claim 87, characterized in that: The tritium solidification product processing unit has a crushing device to process the blocky magnesium tritide into magnesium tritide powder particles. The tritium debinding unit has a hydrolysis device to hydrolyze the magnesium tritide powder particles. The output end of the tritium debinding unit is connected to the tritium physical state conversion unit.

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