A gas-cooled reactor and its combined system with a fusion reactor

Abstract

The present invention discloses a gas-cooled reactor capable of producing tritium, and a combined system thereof with a fusion reactor; wherein the gas-cooled reactor comprises a core, a nuclear fuel sealing isolation layer and a reactor pressure vessel arranged radially from the inside to the outside of the gas-cooled reactor, and also comprises a tritium production module system, the tritium production module system is located at the periphery of the core and between the nuclear fuel sealing isolation layer and the reactor pressure vessel, and the tritium production module system comprises tritium breeding materials, and the tritium breeding materials react with neutrons generated by the core to produce tritium elements. The radiation hazard of high core neutron leakage of the gas-cooled reactor to reactor components and external personnel and equipment can be solved, and the thickness of the reflective layer, the moderation layer and the external shielding body of the gas-cooled reactor can be reduced. In the combined system of the gas-cooled reactor and the fusion reactor, the gas-cooled reactor can provide tritium and / or helium-3 fuel to the fusion reactor to solve the tritium self-sustaining and fuel replenishment problems of the fusion reactor.

Description

Technical Field

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

[0002] At present, the main purposes of research and design of gas-cooled reactors at home and abroad include nuclear power generation, power supply and hydrogen production. Gas-cooled reactors have a higher proportion of high-energy neutrons, a higher core neutron leakage rate and a harder neutron spectrum than water-cooled reactors. They require more fuel loading, higher fissile nuclide enrichment, and bring a more severe neutron irradiation environment. Neutrons leaking from the core, especially fast neutrons with energies higher than 0.1MeV and 1.0MeV, not only cause radiation damage to reactor internals, pressure vessels and other equipment, but also affect the mechanical properties of these equipment as the cumulative neutron injection increases. As a result, key equipment such as pressure vessels age faster, greatly increasing the major safety risks of equipment embrittlement, fracture and failure. At the same time, neutrons leaking from the core of a gas-cooled reactor will also increase the radiation level outside the reactor, bringing radiation risks to external personnel and equipment. Therefore, it is necessary to install neutron moderation and reflection materials such as graphite in the core or the periphery of the gas-cooled reactor, or to increase the thickness of the shielding body outside the reactor or use materials with stronger shielding performance, but these measures will greatly increase the volume, mass and cost of the gas-cooled reactor. If a functional component for producing tritium is set in the gas-cooled reactor, the above problems can be better 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, causing a certain proportion of losses. At the same time, under the current technical level, the collection, purification and treatment of tritium is also difficult to reach 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] Prior art CN103578579A discloses a loading scheme for a fusion-fission subcritical energy reactor core. The core structure includes a plurality of fuel assembly modules arranged in the annular direction of an annular plasma fusion region, each fuel assembly module includes a plurality of fuel assemblies arranged in the poloidal direction of the plasma fusion region, a first wall resistant to high temperature and radiation is arranged on one 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, and an outer shield is arranged outside the tritium-producing blanket.

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

[0006] The designs of the existing technologies cannot achieve a better tritium production effect in gas-cooled reactors, enhance the tritium carrying capacity of the gas medium in gas-cooled reactors, and cannot effectively solve the problem of tritium self-sustaining in fusion reactors and fusion-fission hybrid reactors.

[0007] In view of the above technical problems, the present invention is specially introduced. Summary of the invention

[0008] The main purpose of the present invention is to provide a gas-cooled reactor and a combined system thereof with 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.

[0009] In order to achieve the above-mentioned purpose, according to one aspect of the present invention, a gas-cooled reactor is proposed, comprising 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 comprising a tritium production module system, the tritium production module system 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 material, and the tritium breeding material reacts with neutrons generated by the core to produce tritium elements.

[0010] 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.

[0011] Furthermore, 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.

[0012] 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.

[0013] 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 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 with the second gas acceleration device.

[0014] 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 gas 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.

[0015] 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. The tritium producing region includes tritium breeding material.

[0016] 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 connected to the fluid of the tritium-producing area.

[0017] 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.

[0018] 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, and Ti2O2.

[0019] 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.

[0020] 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.

[0021] 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.

[0022] Furthermore, the core includes a fuel assembly, and along the axial direction of the gas-cooled reactor, the fuel assembly is divided into multiple sections, and the fissile nuclide enrichment of the fuel assembly increases section by section from the air inlet end to the air outlet end of the fuel assembly.

[0023] 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 kinds of fuels with different enrichment levels of fissile nuclides.

[0024] Furthermore, the fuel assembly includes a fuel assembly coolant flow channel, on which a third gas acceleration device is arranged. 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.

[0025] Furthermore, the fuel assembly is cylindrical as a whole and is divided into multiple layers along the radial direction of the gas-cooled reactor. The coolant flow channel of the fuel assembly includes interlayer flow channels, and the interlayer flow channels are gaps of 2mm to 20mm between different layers of fuel assemblies. The fuel assembly is also divided into multiple sectors along the circumferential direction of the gas-cooled reactor, so that each layer of fuel assembly has multiple fuel elements. The coolant flow channel of the fuel assembly also includes axial channels, and each fuel element has multiple axial channels along the axial direction of the gas-cooled reactor.

[0026] Furthermore, the number of axial holes on each fuel element is determined according to the following formula: Where n is the number of 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 from the inside to the outside along the radial direction of the gas-cooled reactor.

[0027] 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 injection rate is 1.5×10 10 ~1.0×10 15n / 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.

[0028] 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%.

[0029] Furthermore, a coolant flow channel and / or a second neutron multiplication layer and / or a second reflection layer and / or a second moderation 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 multiplication layer and / or a third reflection layer and / or a third moderation layer are arranged between the reactor pressure vessel and the tritium production module system.

[0030] Furthermore, the nuclear fuel sealing isolation layer includes a metal container or a shroud, and also includes a fixed support structure. A neutron regulating layer is arranged between the core and the nuclear fuel sealing isolation layer. The neutron regulating 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.

[0031] Furthermore, 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.

[0032] Furthermore, the gas-cooled reactor and gas-cooled fast reactor 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%.

[0033] By applying the above technical solution of the present invention, at least the following beneficial effects are achieved:

[0034] 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 high core of the gas-cooled reactor can be solved, and the thickness of the reflective layer, moderation layer and external shielding body of the gas-cooled reactor can be reduced.

[0035] 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 circulation speed and efficiency of the gas medium. By setting 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 carrying efficiency.

[0036] 3. The gas-cooled reactor can increase the flow rate of the tritium-containing medium in the tritium production module system by setting a second gas acceleration device at the coolant inlet of 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.

[0037] 4. The gas-cooled reactor is provided 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 gas medium parameters entering different systems are adjusted respectively, so that the reactor coolant entering the tritium production module system is coupled with the second gas acceleration device, thereby enhancing the ability of the gas medium in the tritium production module system to carry tritium.

[0038] 5. The tritium production module system of the gas-cooled reactor can better realize the functions of neutron multiplication and production of tritium elements by designing the structure of the neutron multiplication layer, the tritium breeding layer or the structure of the tritium breeding multiplication layer, and 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.

[0039] 6. By designing the fuel assembly in a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor 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 the fuel assembly is increased through temperature and pressure differences, thereby improving the core cooling efficiency, flattening the axial power distribution of the fuel assembly, and improving the core safety.

[0040] 7. In a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor, by designing the shape of the coolant flow channel of the fuel assembly and designing a third gas acceleration device in the coolant flow channel of the fuel assembly, the coolant gas flow rate can be further increased, and the cooling efficiency of the fuel can be enhanced, thereby achieving the tritium production capability under high neutron injection and high temperature conditions.

[0041] In order to achieve the above-mentioned purpose, according to another aspect of the present invention, a combined system of a gas-cooled reactor and a fusion reactor is proposed, comprising a fusion reactor and a gas-cooled reactor, wherein the fusion reactor comprises various fusion reactors using tritium and / or helium-3 as fusion fuel and a fusion-fission hybrid reactor; the combined system also 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 are provided to the fusion reactor through the tritium supply system.

[0042] 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.

[0043] 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.

[0044] 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.

[0045] 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.

[0046] 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.

[0047] 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.

[0048] Furthermore, the fusion reactor provides Pu-239 and / or U-233 to the gas-cooled reactor through a second nuclear fuel supply system.

[0049] By applying the above technical solution of the present invention, at least the following beneficial effects are achieved:

[0050] 1. This combined system is equipped with 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 fuel and / or helium-3 fuel to the fusion reactor or fusion-fission hybrid reactor to solve the problem of tritium self-sustaining and fuel replenishment of fusion reactor and fusion-fission hybrid reactor.

[0051] 2. 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 joint symbiosis of gas-cooled reactor and fusion reactor, increasing the utilization rate of fission fuel, reducing the total radioactive waste, and enhancing the economy of the combined system.

[0052] 3. The combined system 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, 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 economy. BRIEF DESCRIPTION OF THE DRAWINGS

[0053] The accompanying drawings constituting a part of the present invention are used to provide a further understanding of the present invention. The exemplary embodiments of the present invention and their descriptions are used to explain the present invention and do not constitute an improper limitation of the present invention. In the accompanying drawings:

[0054] Figure 1 A longitudinal cross-sectional schematic diagram of the main structure of the gas-cooled reactor of Example 1 is shown;

[0055] Figure 2 A schematic cross-sectional view of a gas-cooled reactor of Embodiment 1 is shown;

[0056] Figure 3 A schematic diagram of the cross-section structure of the gas-cooled reactor of Example 1 is shown;

[0057] Figure 4 A longitudinal cross-sectional schematic diagram of a tritium production module system of a gas-cooled reactor of Example 1 is shown;

[0058] Figure 5 A schematic diagram of the cross-section of the gas-cooled reactor of Example 2 is shown;

[0059] Figure 6 A schematic diagram of the cross-section structure of the gas-cooled reactor of Example 3 is shown;

[0060] Figure 7 A schematic diagram of the combined system of a gas-cooled reactor and a fusion reactor of Example 4 is shown.

[0061] The above drawings include the following reference numerals:

[0062] 1. Reactor core; 11. Fuel assembly; 12. Third gas accelerator; 13. Fuel element; 2. Neutron regulating layer; 3. Nuclear fuel sealing isolation layer;

[0063] 4. Tritium production module system; 41. Second gas acceleration device; 42. Cladding; 43. First neutron multiplying layer; 44. Tritium breeding layer; 45. Tritium breeding multiplying layer; 451. Neutron multiplying section; 452. Tritium breeding section; 46. Tritium pipeline; 47. Baffle; 48. First moderator layer; 49. Irradiation product production layer;

[0064] 5. Reactor pressure vessel; 6. First gas acceleration device; 61. Gas medium physical parameter adjustment system; 62. Connecting pipeline; 7. Diverter plate;

[0065] 8. Tritium supply system; 81. Tritium collection system; 82. Tritium processing and storage system; 821. Tritium extraction system; 822. Tritium purification and separation system; 823. Tritium storage system; 83. Tritium fuel replenishment system;

[0066] 9. Fission fuel two-way supply system; 91. First nuclear fuel supply system; 92. Second nuclear fuel supply system;

[0067] 100. Gas-cooled reactor; 200. Fusion reactor. DETAILED DESCRIPTION

[0068] It should be noted that, in the absence of conflict, the embodiments of the present invention and the features in the embodiments 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.

[0069] The present invention is further described in detail below in conjunction with specific embodiments, and these embodiments cannot be understood as limiting the scope of protection claimed by the present invention. The term "including" when used indicates the existence of a feature, but does not exclude the existence or addition of one or more other features; the orientation or position relationship indicated by the terms "lateral", "upper", "lower", "front", "rear", "left", "right", "top", "bottom", "inside", "outside", etc. is based on the orientation or position relationship shown in the drawings, which is only for the convenience of description, and does not indicate or imply that the device or element referred to must have a specific orientation, be constructed and operated in a specific orientation, and therefore cannot be understood as a limitation on the present invention; in addition, the terms "first" and "second" are only used for descriptive purposes, and cannot be understood as indicating or implying relative importance.

[0070] In the description, it should be noted that, unless otherwise clearly specified and limited, the terms "installed", "connected", and "connected" should be understood in a broad sense. For example, it can be a fixed connection, a detachable connection, or an integral connection; it can be directly connected, or indirectly connected through an intermediate medium, or it can be the internal communication of two components. For ordinary technicians in this field, the specific meanings of the above terms in the present invention can be understood according to specific circumstances. In addition, in the description of the present invention, unless otherwise specified, "plurality" means two or more.

[0071] The gas-cooled reactor proposed in the present application is provided with a tritium production module system, so that the gas-cooled reactor has the function of producing tritium elements.

[0072] Compared with other types of reactors, gas-cooled reactors have three major physical advantages in tritium production. First, gas-cooled reactors have the physical characteristic of a high core neutron leakage rate. By setting up a tritium production module system outside the gas-cooled reactor core, the neutrons leaking from the core react with the tritium breeding materials in the tritium production module system to produce tritium elements. At the same time, the high neutron reaction cross section of its materials is used to reduce the neutron irradiation damage of key equipment such as pressure vessels and the radiation level outside the reactor. The original graphite reflector layer with no added value is replaced with a valuable tritium production module system, and the thickness of the gas-cooled reactor reflector layer, moderator layer and external shielding body can be reduced. Second, the temperature inside the gas-cooled reactor is high, generally exceeding 400-800°C, which is conducive to the release and diffusion of tritium in the tritium production module system, and has excellent conditions for online tritium extraction. Third, the gas coolant of the gas-cooled reactor has a good tritium carrying capacity. The physical and chemical properties of the gas coolant are stable (such as He) and are very different from the physical and chemical properties of tritium (such as carbon dioxide), making it easy to separate and purify tritium.

[0073] Embodiment 1:

[0074] The present invention proposes a gas-cooled reactor, such as Figure 2 As shown, it includes a core 1, a nuclear fuel sealing isolation layer 3 and a reactor pressure vessel 5 arranged from the inside to the outside along the radial direction of the gas-cooled reactor, and also includes a tritium production module system 4, which is located at the periphery of the core 1 and between the nuclear fuel sealing isolation layer 3 and the reactor pressure vessel 5. The tritium production module system 4 includes tritium breeding materials, and the tritium breeding materials react with neutrons generated by the core 1 to produce tritium elements. Among them, the nuclear fuel sealing isolation layer 3 includes a metal container or a shroud, and also includes a fixed support member.

[0075] In a gas-cooled reactor, a tritium production module system 4 is arranged outside the core to produce tritium, thereby solving the radiation hazard of neutron leakage in the high core of the gas-cooled reactor to reactor components and external personnel and equipment, and reducing the thickness of the reflective layer, the moderating layer and the external shielding body of the gas-cooled reactor.

[0076] like Figure 1As shown, the gas-cooled reactor includes a reactor coolant inlet, at which a first gas acceleration device 6 is arranged, and on which a gas medium physical parameter adjustment system 61 is arranged.

[0077] The first gas acceleration device 6 has a structure with a variable cross-sectional area, which is not limited to a tubular structure with a variable 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 gas flow direction, 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 first gas acceleration device 6 has a Laval nozzle designed using the Bernoulli principle and related physical principles, or a structure similar thereto. In addition, in other embodiments, the first gas acceleration device 6 may only include the contraction section therein, and may also play a role in accelerating the gas.

[0078] Specifically, the gas medium physical parameter adjustment system 61 includes a plurality of connecting pipes 62 and a valve assembly. A plurality of holes are opened on the wall surface of the air intake section of the first gas acceleration device 6, which are respectively connected to the plurality of connecting pipes 62. The valve assembly is arranged on the plurality of connecting pipes 62. 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 62.

[0079] In a gas-cooled reactor, by arranging 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 arranging 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 carrying efficiency.

[0080] like Figure 1 As shown, the reactor coolant inlet is connected to the core 1 and the tritium production module system 4 respectively. The gas-cooled reactor 100 includes a diverter plate 7, which is located between the first gas acceleration device 6 and the core 1, and also between the first gas acceleration device 6 and the tritium production module system 4. 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.

[0081] In addition, in this embodiment, the gas parameters of the reactor coolant entering the core 1 and the tritium production module system 4 can be adjusted respectively through the diverter plate 7 .

[0082] like Figure 4As shown, the tritium production module system 4 includes a tritium production module system coolant inlet, and a portion of the reactor coolant flows into the tritium production module system 4 through the tritium production module system coolant inlet after being diverted by the diverter plate. A second gas acceleration device 41 is provided at the tritium production module system coolant inlet.

[0083] The second gas acceleration device 41 has a structure with a variable cross-sectional area, which is not limited to a tubular structure with a variable 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 gas 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 second gas acceleration device 41 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 41 may only include the contraction section therein, which may also play a role in accelerating the gas.

[0084] like Figure 1 As shown, preferably, the diverter plate 7 is connected to the first gas acceleration device 6, and the air flow rate can be controlled by adjusting the opening size at the junction of the diverter plate 7 and the first gas acceleration device 6. Afterwards, according to the parameter range of the gas medium after passing through the first gas acceleration device 6, the space volume between the diverter plate 7 and the reactor pressure vessel 5 and other parameters are adjusted to further adjust the coolant intake amount and parameters entering the core and the tritium production module system respectively. By adjusting the gas parameters successively through the first gas acceleration device 6 and the diverter plate 7, the reactor coolant entering the tritium production module system 4 can be coupled with the second gas acceleration device 41, thereby enhancing the ability of the gas medium in the tritium production module system to carry tritium.

[0085] The specific structure of the tritium production module system 4 in this embodiment will be described in detail below:

[0086] like Figure 3 As shown, the tritium production module system 4 includes a cladding 42 and a tritium production layer group, the cladding 42 is arranged at intervals along the radial direction of the gas-cooled reactor 100, the cladding 42 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 claddings 42. The tritium production layer group includes at least one of a tritium breeding layer 44 and a tritium breeding multiplication layer 45, wherein the tritium breeding layer 44 and the tritium breeding multiplication layer 45 both include a tritium production region, and the tritium production region includes a tritium breeding material.

[0087] A first neutron multiplying layer 43 may also be provided in the tritium producing layer group, and the first neutron multiplying layer 43 includes a neutron multiplying material. The first neutron multiplying layer 43 may be configured together with any one or both of the tritium breeding layer 44 and the tritium breeding multiplying layer 45. Preferably, when there is only the tritium breeding layer 44 in the tritium producing layer group, the first neutron multiplying layer 43 is provided at the same time.

[0088] Combination Figure 3 and Figure 4 As shown, the tritium-producing layer group also includes a tritium pipe 46 for the circulation of reactor coolant and tritium-containing medium. The tritium pipe 46 extends along the axial direction of the gas-cooled reactor 100. A plurality of holes are opened on the wall of the tritium pipe 46 so that the inside of the tritium pipe 46 is fluidically connected to the tritium-producing region.

[0089] The tritium pipeline 46 is a single-layer or multi-layer pipeline. Preferably, the tritium pipeline 46 is a multi-layer pipeline. Figure 4 In the figure, a two-layer pipeline is shown, and a plurality of holes are provided on any layer of the multi-layer pipeline or any multi-layer pipeline wall. Further preferably, along the extension direction of the tritium pipeline 46, the positions of the holes on any two adjacent layers of the pipeline wall on the tritium pipeline are staggered. The tritium production module system makes it easier for the tritium element to be released and diffused from the tritium production module system to the tritium pipeline by setting the tritium pipeline to be multi-layered and providing holes on the pipeline wall, and setting the positions of the holes.

[0090] Furthermore, the tritium pipeline 46 is connected to the second gas acceleration device 41, so that the flow rate of the gas medium entering the tritium pipeline is greatly increased. It is possible to increase the flow rate of the tritium medium contained in the tritium production module system 4, so that the flow rate, pressure, and density of the gas medium entering the different structural layers of the tritium production module system 4 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 the tritium deposited and attached to the wall of the flow channel and the tritium production module system 4, thereby reducing the sedimentation and adsorption loss of tritium. In addition, the second gas acceleration device 41 cooperates with the holes on the wall of the tube, so that the gas flow rate of the tritium pipeline 46 from the outside to the inner layer increases layer by layer, and the pressure decreases layer by layer, thereby further enhancing the efficiency of the release and diffusion of tritium into the tritium pipeline.

[0091] Combination Figure 3 and Figure 4 As shown, in this embodiment, the tritium producing layer group includes a first neutron multiplying layer 43 and a tritium breeding layer 44 arranged radially along the gas-cooled reactor. The tritium breeding layer 44 is located outside the first neutron multiplying layer 43 , and at least a portion of the tritium pipe 46 is located inside the tritium breeding layer 44 .

[0092] The tritium production module system 4 further includes a partition 47 . The partition 47 is arranged between different types of layers in the tritium production layer group, and the partition 47 may also be arranged between the tritium production layer group and other layers.

[0093] In some other embodiments, the tritium production layer group includes a first circulation structure, in which the first neutron multiplication layer 43 and the tritium breeding layer 44 arranged along the radial direction of the reactor are circulated multiple times, and partitions 47 can 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.

[0094] The tritium production module system 4 also includes a tritium penetration-proof layer, which is adjacent to the cladding 42 and adopts a coating or a low-permeability structure. The tritium penetration-proof layer includes oxides and titanium-containing ceramics, wherein the oxides include one or more of the following substances: Cr2O3, Al2O3, Ti2O2, and the titanium-containing ceramics are preferably titanium aluminum carbide ceramics. The tritium penetration-proof layer can effectively prevent the tritium element in the tritium production module system from penetrating to the outside of the tritium production module system to cause loss.

[0095] 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-30 mm.

[0096] The tritium production module system 4 also includes an irradiation product production layer 49, and the material of the irradiation product production layer 49 includes 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 47 are arranged on both sides of the irradiation product production layer 49, and the irradiation product production layer 49 is located outside the tritium breeding layer 44. For other embodiments with irradiation product production requirements, the irradiation product production layer 49 can also be located at other positions of the tritium breeding layer 44, including the inner side or the circumferential side along the radial direction of the gas-cooled reactor.

[0097] The tritium production module system 4 also includes a first reflection layer or a first moderator 48, which is located outside the irradiation product production layer 49. The material of the first reflection layer or the first moderator 48 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. The reflection layer is set here to reflect neutrons, improve neutron utilization, and increase tritium production.

[0098] In some other embodiments, the irradiated product production layer 49 may also be placed between any two layers of the first neutron multiplication layer, the tritium breeding layer, the tritium breeding multiplication layer, the first moderation layer or the first reflection layer, and partitions are provided between the irradiated product production layer and other layers.

[0099] To sum up, preferably, in this embodiment, the tritium production module system includes a cladding 42, a tritium penetration prevention layer, a first neutron multiplication layer 43, a partition 47, a tritium breeding layer 44, a partition 47, an irradiated product production layer 49, a partition 47, a first reflection layer or a first moderation layer 48, a tritium penetration prevention layer, and a cladding 42, which are arranged in sequence from the inside to the outside along the radial direction of the reactor.

[0100] Specifically, the first neutron multiplication layer 43 and the tritium breeding layer 44 both adopt a structure of filling material balls in a ball bed. The first neutron multiplication layer includes neutron multiplication material balls, and the neutron multiplication material balls contain neutron multiplication materials, and the neutron multiplication materials include beryllium and beryllium-containing compounds, such as beryllium, BeO or beryllium-containing ceramics.

[0101] The tritium breeding layer 44 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.

[0102] The diameter of the neutron multiplication material ball and the tritium breeding material ball 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%, so as to achieve better effects of neutron multiplication and tritium breeding.

[0103] Preferably, 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 total enrichment of Li-6 and Li-7 is 100%. The tritium breeder material with a Li-7 enrichment of 50%-92.5% is arranged at a position close to the reactor core, and the tritium breeder material with a Li-6 enrichment of 50%-90% is arranged at a position far from the reactor core.

[0104] 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). The neutron energy spectrum is "softened" by slowing down the neutrons through the previous material layer, increasing the proportion of low-energy and thermal neutrons and the tritium production rate with Li-6, ultimately reducing the manufacturing cost of the breeding material and increasing the tritium production rate.

[0105] The tritium production module system also includes a coolant channel, which has a similar function to the tritium pipeline and is used for the circulation of reactor coolant and / or tritium-containing medium. The coolant channel is arranged in the gaps between layers in the tritium production module system, and / or inside the cladding and / or partition.

[0106] Preferably, the thickness of the cladding and / or the partition is greater than 1 mm. If a coolant pipeline is provided in the cladding and / or the partition, the thickness of the cladding and / or the partition having the coolant channel is greater than 3 mm.

[0107] 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 of 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.

[0108] The shape of the tritium production module system includes one or more of the following shapes: 360° overall hollow circular cylinder, 1° to 359° hollow arc cylinder, cylinder, polygonal prism, trapezoidal cross-section cylinder, fan-shaped cross-section cylinder, and cube.

[0109] In the present application, the thickness of the tritium production module system along the radial direction of the reactor is 1 cm-100 cm. Preferably, the thickness of the tritium production module system is 15 cm-60 cm.

[0110] Preferably, if Figure 3 As shown, the tritium production module system is in the shape of a circular column, which 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 seamlessly spliced ​​in the circumferential direction, and the number of tritium production sub-modules is in the range of 4-24. That is, the shape of the tritium production sub-module is a columnar fan cross-section with an angle of 15° to 90°.

[0111] More preferably, if Figure 3 As shown, partitions are arranged between adjacent tritium-producing submodules to prevent the materials of adjacent tritium-producing submodules from directly contacting each other. The tritium pipelines surround the core in the tritium breeding layer along the circumference, and 2-6 tritium pipelines are arranged in each tritium-producing submodule.

[0112] The tritium production module system is completely surrounded by the reactor in the circumferential direction and is composed of a certain number of tritium production sub-modules, so that the reactor can achieve the maximum tritium production effect. When a part of the tritium production sub-modules has problems, it is convenient to replace them, thereby ensuring the stability of the reactor's tritium production.

[0113] like Figure 1 As shown, the core 1 includes a fuel assembly 11. Along the axial direction of the gas-cooled reactor, the fuel assembly 11 is divided into multiple sections. From the air inlet end to the air outlet end of the fuel assembly 11, the fissile nuclide enrichment of the fuel assembly 11 increases section by section. The flow rate of the flow channel gas in the core and the fuel assembly is increased through the temperature difference and the pressure difference, thereby improving the core cooling efficiency, flattening the axial power distribution of the fuel assembly, and improving the core safety.

[0114] Preferably, the fuel assembly 11 is divided into 3-8 sections along the axial direction of the gas-cooled reactor 100, and the multi-section fuel assembly 11 uses 3-4 kinds of fuels with different enrichment levels of fissile nuclides.

[0115] Preferably, the fuel assembly 11 includes a fuel assembly coolant flow channel, and a third gas acceleration device 12 is arranged on the fuel assembly coolant flow channel. The third gas acceleration device 12 adopts a structure similar to the first gas acceleration device 6 and the second gas acceleration device 41, and adopts a cross-sectional area variation structure, including a contraction section, or a contraction section, a narrow throat section and an expansion section connected in sequence along the gas flow direction. Preferably, a Laval nozzle structure can be adopted. The third gas acceleration device is designed in the fuel assembly coolant flow channel to further increase the coolant gas flow rate and enhance the cooling efficiency of the fuel.

[0116] It should be noted that the above scheme of segmenting the fuel assembly and providing the third gas acceleration device 12 is more suitable for a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor, and may not be adopted for other types of gas-cooled reactors.

[0117] A coolant flow channel and / or a second neutron multiplication layer and / or a second reflection layer and / or a second moderation layer may be arranged between the nuclear fuel sealing isolation layer 3 and the tritium production module system 4; a coolant flow channel and / or a third neutron multiplication layer and / or a third reflection layer and / or a third moderation layer may be arranged between the reactor pressure vessel 5 and the tritium production module system 4.

[0118] The nuclear fuel sealing isolation layer 3 includes a metal container or a panel, and also includes a fixed support member. Figure 2 As shown, a neutron regulating layer 2 is arranged between the core 1 and the nuclear fuel sealing isolation layer 3, and the neutron regulating layer 2 includes a coolant flow channel, and / or a fourth neutron multiplication layer and / or a fourth reflection layer and / or a fourth moderation layer.

[0119] For a general gas-cooled reactor, a fourth neutron multiplication layer is provided in the neutron regulating layer 2. For a cold fast reactor, a fourth moderator layer may be provided in the neutron regulating layer 2 of the gas-cooled reactor.

[0120] The thermal neutron injection rate of the tritium production module system 4 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 100 is a gas-cooled fast reactor, the thermal neutron injection 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 injection rate is 5.0×10 9 ~1.0×10 13 n / cm 2 ·s.

[0121] 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) in engineering.

[0122] The shapes of fuel elements include: spherical, cylindrical, plate-shaped, block-shaped, cross-plate-shaped, curved plate-shaped, and hollow cylindrical. The cross-sectional shapes of columnar fuel elements include: circular, regular polygonal (such as square, regular hexagon, regular octagon, etc.). The shapes of the inner and outer sides of the cross-sectional shapes of hollow columnar fuel elements include: circular, regular polygonal (such as square, regular hexagon, regular octagon, etc.), and the inner and outer sides may be the same shape or different shapes.

[0123] The core fuel is a substance containing uranium, thorium and plutonium, including AO2, AC, AN, or MOX ceramic fuel, or TRISO type fuel with coated particles. A is one of uranium, thorium and plutonium, and MOX includes any two or three of uranium, thorium and plutonium.

[0124] 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%.

[0125] Embodiment 2:

[0126] The structure of the gas-cooled reactor in this embodiment is basically the same as that in Embodiment 1, except that the structure of the tritium production module system 4 is different. Figure 5 As shown, the tritium production module system in Embodiment 2 is composed of a cladding 42 and a tritium multiplication layer 45 between the claddings. A tritium penetration-proof layer adjacent to the cladding 42 may also be provided.

[0127] Specifically, the tritium-producing layer group in this embodiment includes a tritium multiplication layer 45, and the tritium multiplication layer 45 includes a neutron multiplication portion 451 and a cylindrical tritium multiplication portion 452. A plurality of tritium multiplication portions 452 are evenly arranged in the neutron multiplication portion 451, so that the neutron injection in each tritium multiplication portion 452 is at the same order of magnitude. Preferably, a partition 47 is provided on the periphery of the cylindrical tritium multiplication portion 452 to separate the materials of the neutron multiplication portion 451 and the tritium multiplication portion 452. The volume ratio of the neutron multiplication portion 451 to the tritium multiplication portion 452 is in the range of 2:1 to 8:1, and the tritium pipes 46 are arranged in an array in the tritium multiplication portion 452.

[0128] Preferably, the number of tritium breeding units 452 in each tritium producing submodule does not exceed 6. Figure 5Three are shown. The difference in distance between the material at all positions in the tritium breeding section 452 and the nearest tritium pipe 46 is made to be no more than 50% of the diameter of the tritium breeding section 452 , thereby facilitating the release and diffusion of tritium elements in the tritium breeding section 452 .

[0129] In some other embodiments, the tritium-producing layer group includes a second circulation structure, in which the first neutron multiplying layer 43, the tritium breeding layer 44 and the tritium breeding multiplying layer 45 arranged along the radial direction of the reactor are circulated multiple times. A partition 47 can be arranged between different layers. The shape and structure of the first neutron multiplying layer 43 and the tritium breeding layer 44 refer to Example 1. This circulation structure has a high utilization rate of neutrons in the reactor.

[0130] In some other embodiments, the tritium producing layer group may be configured as a combination of a tritium breeding multiplication layer 45 and a first neutron multiplication layer 43 .

[0131] Specifically, the tritium multiplication layer 45 can be configured as a mixture of neutron multiplication material balls and tritium multiplication material balls. The tritium multiplication layer 45 can also include tritium multiplication material balls, the core of which has tritium multiplication material, and the shell of which has neutron multiplication material.

[0132] If the tritium multiplication layer 45 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 in the 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 0.1mm-10mm, and the filling rate is 40%-80%. Preferably, the diameter is 0.2mm-2mm, and the filling rate is 50%-70%. The effect of neutron multiplication and tritium multiplication is better.

[0133] It should be noted that the structure of the tritium multiplication layer 45 described in this embodiment is only preferred, and the structure of the tritium multiplication layer 45 is not limited to Figure 5 For example, the cross-sectional shape of the tritium multiplication portion 452 may be other shapes, or the tritium multiplication multiplication layer 45 may only include tritium multiplication multiplication material balls.

[0134] In this embodiment, preferably, the irradiation product production layer 49 is not provided. At the same time, the neutron multiplication unit 451 is used as a neutron reflection layer, and the first reflection layer or the first moderation layer 48 may not be provided in the tritium production module system. Thus, the structure of the tritium production module system is greatly simplified.

[0135] In addition, in order to take isotope production into consideration, no more than one half of the total amount of material in the tritium breeding section 452 can be filled with isotope production material.

[0136] In some other embodiments, an irradiation product production layer 49 or a first reflection layer or a first moderation layer 48 may also be provided in the tritium production module system described in this embodiment.

[0137] In summary, from the above description, it can be seen that Embodiment 1 and Embodiment 2 at least achieve the following technical effects:

[0138] 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 high core of the gas-cooled reactor can be solved, and the thickness of the reflective layer, moderation layer and external shielding body of the gas-cooled reactor can be reduced.

[0139] 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 circulation speed and efficiency of the gas medium. By setting 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 carrying efficiency.

[0140] 3. The gas-cooled reactor can increase the flow rate of the tritium-containing medium in the tritium production module system by setting a second gas acceleration device at the coolant inlet of 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.

[0141] 4. The gas-cooled reactor is provided 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 gas medium parameters entering different systems are adjusted respectively, so that the reactor coolant entering the tritium production module system is coupled with the second gas acceleration device, thereby enhancing the ability of the gas medium in the tritium production module system to carry tritium.

[0142] 5. The tritium production module system of the gas-cooled reactor can better realize the functions of neutron multiplication and production of tritium elements by designing the structure of the neutron multiplication layer, the tritium breeding layer or the structure of the tritium breeding multiplication layer, and 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.

[0143] Embodiment 3:

[0144] The gas-cooled reactor structure in this embodiment is basically the same as that in Embodiment 1 and Embodiment 2. Figure 6 As shown, a gas-cooled reactor which is substantially the same as the tritium production module system 4 of Example 1 is taken as an example. The difference is that the gas-cooled reactor of this embodiment is a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor.

[0145] Specifically, in order to further improve the neutron injection rate at the tritium production module system, it is preferred that the core 1 here adopts arc columnar fuel elements arranged in a compact array. For a high-flux gas-cooled reactor, a coolant channel can be set in the neutron adjustment layer 2. For a high-flux gas-cooled fast reactor, a coolant channel can be set in the neutron adjustment layer 2, and a fourth moderator layer or a fourth reflector layer can be set.

[0146] 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%.

[0147] Combination Figure 1 As shown, Figure 1 As shown, the core 1 includes a fuel assembly 11. Along the axial direction of the gas-cooled reactor, the fuel assembly 11 is divided into multiple sections. From the air inlet end to the air outlet end of the fuel assembly 11, the fissile nuclide enrichment of the fuel assembly 11 increases section by section.

[0148] Preferably, the fuel assembly 11 is divided into 3-8 sections along the axial direction of the gas-cooled reactor 100, and the multi-section fuel assembly 11 uses 3-4 kinds of fuels with different enrichment levels of fissile nuclides.

[0149] By designing the fuel assembly in a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor 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 the fuel assembly is increased through temperature and pressure differences, thereby improving the core cooling efficiency, flattening the axial power distribution of the fuel assembly, and improving the core safety.

[0150] Preferably, the fuel assembly 11 includes a fuel assembly coolant flow channel, and a third gas acceleration device 12 is provided on the fuel assembly coolant flow channel. The third gas acceleration device 12 adopts a structure similar to the first gas acceleration device 6 and the second gas acceleration device 41, and preferably, a Laval nozzle structure can be adopted. The third gas acceleration device is designed in the fuel assembly coolant flow channel to further increase the coolant gas flow rate and enhance the cooling efficiency of the fuel.

[0151] like Figure 6 As shown, the fuel assembly 11 is cylindrical as a whole and includes a plurality of fuel elements 13. It is divided into multiple layers along the radial direction of the gas-cooled reactor, and the coolant flow channel of the fuel assembly includes an interlayer flow channel, which is a gap of 2 mm to 20 mm between fuel assemblies 11 of different layers.

[0152] In addition, the fuel assembly 11 is further divided into a plurality of sectors along the circumferential direction of the gas-cooled reactor 100, and the angles of each sector may be different, so that each layer of the fuel assembly 11 has a plurality of fuel elements 13. The fuel assembly coolant flow channel also includes an axial channel, and each fuel element 13 has a plurality of axial channels along the axial direction of the gas-cooled reactor 100.

[0153] Specifically, if Figure 6 As shown, the number of axial holes on each fuel element 13 is determined according to the following formula: Where n is the number of axial holes, θ is the central angle of the sector where the fuel element 13 is located, and m is the number of layers where the fuel element 13 is located from the inside to the outside along the radial direction of the gas-cooled reactor. This design enables each fuel element to have a suitable number of axial holes, which is beneficial to improving the cooling efficiency of the entire fuel assembly 11.

[0154] In a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor, the shape of the coolant flow channel of the fuel assembly is designed, and a third gas acceleration device is designed in the coolant flow channel of the fuel assembly to further increase the coolant gas flow rate and enhance the cooling efficiency of the fuel, 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.

[0155] The thermal neutron injection rate of the tritium production module system 4 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 4 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.

[0156] In summary, from the above description, it can be seen that this embodiment also achieves at least the following technical effects:

[0157] 1. By designing the fuel assembly in a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor 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 the fuel assembly is increased through temperature and pressure differences, thereby improving the core cooling efficiency, flattening the axial power distribution of the fuel assembly, and improving the core safety.

[0158] 2. In a high-flux gas-cooled reactor or a high-flux gas-cooled fast reactor, by designing the shape of the coolant flow channel of the fuel assembly and designing a third gas acceleration device in the coolant flow channel of the fuel assembly, the coolant gas flow rate can be further increased, and the cooling efficiency of the fuel can be enhanced, thereby achieving the tritium production capability under high neutron injection and high temperature conditions.

[0159] 3. By setting the first gas acceleration device in the gas-cooled reactor, setting coolant flow channels in the core and fuel assemblies, and the third gas acceleration device, the efficient cooling capacity of the core is guaranteed, and the temperature of the gas-cooled reactor fuel and the materials of the internal components of the reactor is controlled, thereby realizing the high-throughput gas-cooled reactor technology.

[0160] Embodiment 4:

[0161] Based on Example 1, Example 2 and Example 3, this example further proposes a combined system of a gas-cooled reactor and a fusion reactor, such as Figure 7 As shown, it includes any one of the gas-cooled reactors 100 described in the aforementioned embodiment 1, embodiment 2 or embodiment 3, and also includes a fusion reactor 200.

[0162] It should be noted that the fusion reactor 200 mentioned in the present application includes all fusion reactors using tritium and / or helium-3 (He-3) as fusion fuel and fusion-fission hybrid reactors.

[0163] The combined system also includes a tritium supply system 8, which is connected to the gas-cooled reactor 100 and also connected to the fusion reactor 200. The gas-cooled reactor 100 produces tritium and provides tritium fuel and / or helium-3 fuel for the fusion reactor 200.

[0164] This combined system sets up a tritium supply system, and collects, processes, stores and transports the tritium produced by the gas-cooled reactor through the tritium supply system. It can provide tritium and / or helium-3 as fuel to fusion reactors or fusion-fission hybrid reactors, thereby solving the problem of tritium self-sustaining and fuel replenishment of fusion reactors and fusion-fission hybrid reactors.

[0165] Specifically, the tritium supply system 8 includes a tritium collection system 81 , a tritium processing and storage system 82 , and a tritium fuel replenishment system 83 which are connected in sequence. The tritium collection system 81 is connected to the gas-cooled reactor 100 , and the tritium fuel replenishment system 83 is connected to the fusion reactor 200 .

[0166] The tritium processing and storage system 82 includes: a tritium extraction system 821, a tritium purification and separation system 822, a tritium storage system 823 and a tritium monitoring system; the tritium monitoring system is associated with the tritium extraction system 821, the tritium purification and separation system 822 and the tritium storage system 823, and monitors the equipment and facilities of each system.

[0167] 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 82, so as to achieve different monitoring functions.

[0168] The tritium collection system 81 includes: a tritium purification system, a tritium diversion system, a gas cooling and a tritium conversion / catalysis system; the tritium fuel replenishment system 83 includes: a feed pretreatment system and a tritium injection system, and the tritium injection system is connected to the fusion reactor 200. After the feed pretreatment system separates the tritium fuel and the helium-3 fuel, the tritium injection system injects them into the fusion reactor 200 respectively.

[0169] like Figure 7 As shown, the input of the tritium collection system 81 is in communication with the tritium production module system 4 of the gas-cooled reactor 100 , and the reactor coolant and tritium-containing medium in the tritium production module system 4 enter the tritium supply system 8 .

[0170] Furthermore, the input of the tritium collection system 81 is connected to the core 1 of the gas-cooled reactor 100, and the reactor coolant in the core 1 enters the tritium supply system 8. The reactor coolant after separation and purification to remove tritium is returned to the gas-cooled reactor 100 for reuse.

[0171] The combined system is configured to connect the input of the tritium collection system to the tritium production module system and the core of the gas-cooled reactor. When there is no need to extract or purify the core coolant, 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 economy.

[0172] The combined system further includes a fission fuel bidirectional supply system 9, including a first nuclear fuel supply system 91 and a second nuclear fuel supply system 92. The gas-cooled reactor 100 and the fusion reactor 200 provide nuclear fuel to each other through the fission fuel bidirectional supply system 9. The nuclear fuel here may include fission fuel, conversion fuel or fusion fuel.

[0173] Specifically, the gas-cooled reactor 100 provides one or more of the following materials to the fusion reactor 200 through the first nuclear fuel supply system 91: depleted uranium, Th-232, U-238 and Pu-239 initial fuel. These materials may be used as conversion fuels for fusion reactors or fission materials for fusion-fission hybrid reactors.

[0174] The fusion reactor 200 provides Pu-239 and / or U-233 to the gas-cooled reactor 100 through the second nuclear fuel supply system 92. Here, Pu-239 is used as MOX fuel of the gas-cooled reactor.

[0175] Specifically, the first nuclear fuel supply system 91 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.

[0176] The second nuclear fuel supply system 92 includes a nuclear fuel cladding receiving and disintegration unit, a cladding shear decomposition unit, a nuclide separation and purification unit, and a gas-cooled reactor nuclear fuel manufacturing unit, which are connected in sequence.

[0177] The first nuclear fuel supply system 91 and the second nuclear fuel supply system 92 both further include a radioactive waste treatment and storage unit and a tritium enrichment unit. The highly tritium-containing 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 a tritium collection system or a tritium treatment and storage system.

[0178] 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 between the gas-cooled reactor and the fusion reactor or the fusion-fission hybrid reactor, increasing the utilization rate of the fission fuel, reducing the total radioactive waste, and enhancing the economy of the combined system.

[0179] In summary, from the above description, it can be seen that this embodiment achieves at least the following technical effects:

[0180] 1. This combined system is equipped with 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 fuel and / or helium-3 fuel to the fusion reactor or fusion-fission hybrid reactor to solve the problem of tritium self-sustaining and fuel replenishment of fusion reactor and fusion-fission hybrid reactor.

[0181] 2. 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 between the gas-cooled reactor and the fusion reactor or the fusion-fission hybrid reactor, increasing the utilization rate of the fission fuel, reducing the total radioactive waste, and enhancing the economy of the combined system.

[0182] 3. The combined system 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, 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 economy.

[0183] The above description is only a preferred embodiment of the present invention and is not intended to limit the present invention. For those skilled in the art, the present invention may have various modifications and variations. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention shall be included in the protection scope of the present invention.

Claims

1. A gas-cooled reactor, comprising a core (1), a nuclear fuel sealing isolation layer (3) and a reactor pressure vessel (5) arranged from inside to outside along the radial direction of the gas-cooled reactor (100), characterized in that: It also includes a tritium production module system (4), which is located at the periphery of the core (1) and between the nuclear fuel sealing isolation layer (3) and the reactor pressure vessel (5). The tritium production module system (4) includes tritium breeding material, and the tritium breeding material reacts with neutrons generated by the core (1) to produce tritium elements.

2. The gas-cooled reactor according to claim 1, characterized in that: The gas-cooled reactor (100) comprises a reactor coolant inlet, a first gas acceleration device (6) is arranged at the reactor coolant inlet, and a gas medium physical parameter adjustment system (61) is arranged on the first gas acceleration device (6).

3. The gas-cooled reactor according to claim 2, characterized in that: The gas medium physical parameter regulating system (61) comprises a plurality of connecting pipes (62) and a valve assembly. A plurality of holes are provided on the wall surface of the air inlet section of the first gas acceleration device (6), respectively connected to the plurality of connecting pipes (62). The valve assembly is arranged on the plurality of connecting pipes (62). The valve assembly comprises a regulating valve, a constant pressure check valve and / or a variable pressure check valve.

4. The gas-cooled reactor according to claim 3, characterized in that: The reactor coolant inlet is connected to the core (1) and the tritium production module system (4) respectively. The gas-cooled reactor (100) includes a diverter plate (7). The diverter plate (7) is located between the first gas acceleration device (6) and the core (1), and also between the first gas acceleration device (6) and the tritium production module system (4). The diverter plate (7) isolates the reactor coolant entering the core (1) from the reactor coolant entering the tritium production module system (4).

5. The gas-cooled reactor according to claim 4, characterized in that: The tritium production module system (4) comprises a tritium production module system coolant inlet, and the tritium production module system coolant inlet is provided with a second gas acceleration device (41); By adjusting the space between the diverter plate (7) and the reactor pressure vessel (5), the intake amount and parameters of the reactor coolant entering the second gas acceleration device (41) are adjusted, and the reactor coolant entering the tritium production module system (4) is coupled to the second gas acceleration device (41).

6. The gas-cooled reactor according to claim 5, characterized in that: The first gas acceleration device (6) and / or the second gas acceleration device (41) 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.

7. The gas-cooled reactor according to any one of claims 1 to 6, characterized in that: The tritium production module system (4) further comprises a cladding (42) and a tritium production layer group, wherein the cladding (42) is arranged at intervals along the radial direction of the gas-cooled reactor (100), and the tritium production layer group is located between the claddings (42), and the tritium production layer group comprises a tritium breeding layer (44) and / or a tritium breeding multiplication layer (45), and the tritium breeding layer (44) and the tritium breeding multiplication layer (45) both comprise a tritium production region, and the tritium production region comprises the tritium breeding material.

8. The gas-cooled reactor according to claim 7, characterized in that: The tritium-producing layer group also includes a tritium pipe (46) for the circulation of the reactor coolant and the tritium-containing medium. The tritium pipe (46) extends along the axial direction of the gas-cooled reactor (100). A plurality of holes are provided on the wall of the tritium pipe (46), so that the interior of the tritium pipe (46) is fluidically connected to the tritium-producing region.

9. The gas-cooled reactor according to claim 8, characterized in that: The tritium producing layer group comprises a first neutron multiplying layer (43) and a tritium breeding layer (44) arranged along the radial direction of the gas-cooled reactor (100); the tritium breeding layer (44) is located outside the first neutron multiplying layer (43); the first neutron multiplying layer (43) comprises a neutron multiplying material; and the tritium pipe (46) is at least partially located inside the tritium breeding layer (44).

10. The gas-cooled reactor according to claim 9, characterized in that: The tritium production module system (4) further includes a partition (47), wherein the partition (47) is arranged between different types of layers in the tritium production layer group and / or between the tritium production layer group and other layers; the tritium production module system (4) further includes an anti-tritium penetration layer, wherein the anti-tritium penetration layer is adjacent to the cladding (42), and the anti-tritium penetration layer includes oxides and titanium-containing ceramics, wherein the oxides include one or more of the following substances: Cr2O3, Al2O3, Ti2O2.

11. The gas-cooled reactor according to claim 10, characterized in that: The tritium production module system (4) further comprises an irradiated product production layer (49), the material of the irradiated product production layer (49) comprising 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 (47) are arranged on both sides of the irradiated product production layer (49), and the irradiated product production layer (49) is located outside the tritium breeding layer (44).

12. The gas-cooled reactor according to claim 11, characterized in that: The tritium production module system (4) further comprises a first reflection layer or a first moderator layer (48), wherein the first reflection layer or the first moderator layer (48) is located outside the irradiation product production layer (49), and the material of the first reflection layer or the first moderator layer (48) comprises 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.

13. The gas-cooled reactor according to claim 8, characterized in that: The tritium-producing layer group comprises a tritium multiplication layer (45), wherein the tritium multiplication layer (45) comprises a neutron multiplication section (451) and a cylindrical tritium multiplication section (452), a plurality of tritium multiplication sections (452) are evenly arranged in the neutron multiplication section (451), a volume ratio of the neutron multiplication section (451) to the tritium multiplication section (452) is in the range of 2:1 to 8:1, and the tritium pipes (46) are arranged in an array in the tritium multiplication section (452).

14. The gas-cooled reactor according to claim 6, characterized in that: The core (1) comprises a fuel assembly (11). Along the axial direction of the gas-cooled reactor (100), the fuel assembly (11) is divided into a plurality of sections. From the air inlet end to the air outlet end of the fuel assembly (11), the fissile nuclide enrichment of the fuel assembly (11) increases section by section.

15. The gas-cooled reactor according to claim 14, characterized in that: The fuel assembly (11) is divided into 3-8 sections along the axial direction of the gas-cooled reactor (100), and the multiple sections of the fuel assembly (11) use 3-4 types of fuels with fissile nuclides of different enrichment degrees.

16. The gas-cooled reactor according to claim 15, characterized in that: The fuel assembly (11) comprises a fuel assembly coolant flow channel, on which a third gas acceleration device (12) is arranged. The third gas acceleration device (12) adopts a structure with a variable cross-sectional area, comprising the contraction section, or the contraction section, the narrow throat section and the expansion section connected in sequence along the gas flow direction.

17. The gas-cooled reactor according to claim 16, characterized in that: The fuel assembly (11) is cylindrical as a whole and is divided into multiple layers along the radial direction of the gas-cooled reactor (100). The coolant flow channel of the fuel assembly includes an interlayer flow channel, and the interlayer flow channel is a gap of 2 mm to 20 mm between different layers of the fuel assemblies (11). The fuel assembly (11) is also divided into multiple sectors along the circumferential direction of the gas-cooled reactor (100), so that each layer of the fuel assembly (11) has multiple fuel elements (13). The coolant flow channel of the fuel assembly also includes an axial channel, and each fuel element (13) has multiple axial channels along the axial direction of the gas-cooled reactor (100).

18. The gas-cooled reactor according to claim 17, characterized in that: The number of axial holes on each fuel element (13) 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 (13) is located, and m is the number of layers where the fuel element (13) is located along the radial direction of the gas-cooled stack from inside to outside.

19. The gas-cooled reactor according to any one of claims 14 to 18, characterized in that: The gas-cooled reactor (100) 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 (4) 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 (4) 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.

20. The gas-cooled reactor according to claim 19, 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%.

21. The gas-cooled reactor according to any one of claims 8 to 13, characterized in that: A coolant flow channel and / or a second neutron multiplication layer and / or a second reflection layer and / or a second moderation layer are arranged between the nuclear fuel sealing isolation layer (3) and the tritium production module system (4); and the coolant flow channel and / or a third neutron multiplication layer and / or a third reflection layer and / or a third moderation layer are arranged between the reactor pressure vessel (5) and the tritium production module system (4).

22. The gas-cooled reactor according to claim 21, characterized in that: The nuclear fuel sealing isolation layer (3) comprises a metal container or a shroud, and also comprises a fixed support member. A neutron regulating layer (2) is arranged between the core (1) and the nuclear fuel sealing isolation layer (3), and the neutron regulating layer (2) comprises the coolant flow channel and / or the fourth neutron multiplication layer and / or the fourth reflection layer and / or the fourth moderation layer.

23. The gas-cooled reactor according to claim 22, characterized in that: The thermal neutron fluence rate of the tritium production module system (4) of the gas-cooled reactor (100) 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 (100) is a gas-cooled fast reactor, the thermal neutron injection 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 injection rate is 5.0×10 9 ~1.0×10 13 n / cm 2 ·s.

24. The gas-cooled reactor according to claim 20, characterized in that: The gas-cooled reactor (100) 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%.

25. A combined system of a gas-cooled reactor and a fusion reactor, characterized in that: The fusion reactor (200) further comprises the gas-cooled reactor (100) according to any one of claims 1 to 24, wherein the fusion reactor (200) 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 (8), wherein the tritium supply system (8) is connected to the gas-cooled reactor (100) and also connected to the fusion reactor (200). The gas-cooled reactor (100) produces tritium and provides tritium fuel and / or helium-3 fuel to the fusion reactor (200) through the tritium supply system (8).

26. The combined system according to claim 25, characterized in that: The tritium supply system (8) includes a tritium collection system (81), a tritium processing and storage system (82), and a tritium fuel replenishment system (83) which are connected in sequence. The tritium collection system (81) is connected to the gas-cooled reactor (100), and the tritium fuel replenishment system (83) is connected to the fusion reactor (200).

27. The combined system according to claim 26, characterized in that: The tritium processing and storage system (82) includes: a tritium extraction system (821), a tritium purification and separation system (822), a tritium storage system (823) and a tritium monitoring system; the tritium monitoring system is associated with the tritium extraction system (821), the tritium purification and separation system (822) and the tritium storage system (823) to monitor the equipment and facilities in each system.

28. The combined system according to claim 27, characterized in that: The tritium collection system (81) includes: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion / catalysis system; the tritium fuel replenishment system (83) includes: a fuel pretreatment system and a tritium injection system.

29. The combined system according to claim 26, characterized in that: The input of the tritium collection system (81) is connected to the tritium production module system (4) of the gas-cooled reactor (100), and the reactor coolant and tritium-containing medium in the tritium production module system (4) enter the tritium supply system (8).

30. The combined system according to claim 29, characterized in that: The input of the tritium collection system (81) is connected to the core (1) of the gas-cooled reactor (100), and the reactor coolant in the core (1) enters the tritium supply system (8). After separation and purification to remove tritium, the reactor coolant returns to the gas-cooled reactor (100) for reuse.

31. The combined system of claim 25, wherein: The combined system further comprises a fission fuel bidirectional supply system (9), comprising a first nuclear fuel supply system (91) and a second nuclear fuel supply system (92); the gas-cooled reactor (100) provides one or more of the following substances to the fusion reactor (200) through the first nuclear fuel supply system (91): depleted uranium, Th-232, U-238 and Pu-239 initial fuel.

32. The combined system according to claim 31, characterized in that: The fusion reactor (200) provides Pu-239 and / or U-233 to the gas-cooled reactor (100) through the second nuclear fuel supply system (92).

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