Energy conversion system and use thereof

Abstract

The application discloses an energy conversion system and application thereof. The system comprises a three-machine integrated system, a nuclear reactor, a regenerator and a precooler. The regenerator and the precooler are arranged on the extension lines of the axis of the nuclear reactor, and the three-machine integrated system is arranged above the nuclear reactor. The three-machine integrated system comprises a compressor, a generator and a turbine which are coaxially arranged. The generator is arranged between the compressor and the turbine. The compressor is used for pressurizing helium-xenon gas. The nuclear reactor is used for providing heat for the helium-xenon gas. A third helium-xenon gas outlet, a heat fluid channel of the regenerator, the precooler and a first helium-xenon gas inlet are sequentially connected to form a helium-xenon gas circulation loop. The regenerator and the precooler are both printed circuit board heat exchangers. The system can simultaneously meet the requirements of high heat conversion efficiency, high power generation efficiency, low system size and low system weight.

Description

Technical Field

[0001] This invention relates to an energy conversion system and its application. Background Technology

[0002] Vehicle-mounted nuclear reactors offer advantages such as high operating power, long endurance, independence from sunlight and wind, high safety, and high reliability. They can meet the growing defense missions in remote land areas, at sea, and in space, including tasks such as remote outposts, radar power stations, space reconnaissance, intelligence gathering, and underwater patrols. Due to limitations imposed by truck mounting conditions, high efficiency and lightweight design are key objectives for energy conversion systems.

[0003] The Brayton cycle is an ideal thermodynamic cycle for simple cycle gas turbines. However, traditional Brayton cycle designs suffer from drawbacks such as multiple independent units, low conversion efficiency, large space requirements, and low reliability, failing to meet the requirements for small-scale, high-efficiency, and lightweight on-board reactors. Current technologies addressing the issue of lightweight reactor shielding typically focus on the development of shielding materials or the structural design of shielding systems. This includes: studying the mechanical properties of various composite shielding materials, testing their density, hardness, elastic modulus, and other physical properties to improve the strength and reliability of the shielding system; researching the matrix shielding performance of various composite shielding materials, analyzing the shielding effects of different component composites on neutrons and photons, and determining the optimal material composition; and studying the corrosion resistance, radiation resistance, and manufacturing processes of shielding materials to complete the selection of the overall shielding material.

[0004] Inert gases and their binary mixtures are considered ideal working fluids for space propulsion systems and ground-based power plants employing closed Brayton cycles and gas turbine engines. For nuclear power systems, helium is commonly used as the working fluid in Brayton cycles due to its high stability, chemical compatibility, and thermal conductivity. However, helium also has some drawbacks, such as the need for high temperatures in the power cycle and its difficulty in compression. These characteristics pose significant challenges to the design of structural materials for cycle components and the turbomachinery. Furthermore, helium's low molar mass results in a larger volumetric flow rate for the same mass flow rate, leading to relatively large volumes of regenerators and precoolers in the system. Additionally, helium's high specific heat capacity at constant pressure results in a large enthalpy change in the turbomachinery at a fixed pressure ratio, requiring an increase in the number of compressor stages to achieve the design pressure ratio, which also increases the size and mass of the turbomachinery. Considering factors such as reducing reactor structural material requirements, minimizing technical difficulties, and improving reactor safety and applicability, adding a certain proportion of inert gases to helium can significantly reduce aerodynamic loads, thereby reducing the size and mass of the turbine machinery and power system. Xenon has the largest molar mass, giving it the greatest ability to adjust the working fluid properties. Adding only a small amount of xenon can effectively increase the molar mass of the working fluid, thus having a relatively small impact on its thermodynamic properties. Meanwhile, the helium-xenon mixture has a higher heat transfer coefficient, which positively affects the system's thermodynamic performance. Therefore, xenon was chosen as the optimal working fluid mixture. Other space reactors or mobile nuclear power systems have also used helium-xenon mixtures as working fluids in their Brayton cycles, a typical example being the Holos helium-cooled reactor designed by the United States.

[0005] Although existing energy conversion systems based on the traditional Brayton cycle can improve their heat transfer coefficient by using a helium-xenon mixture as the working fluid, the requirements for high heat conversion efficiency, high power generation efficiency, low system size, and low system weight cannot be met simultaneously. Summary of the Invention

[0006] This invention addresses the technical problems of low heat conversion efficiency, low power generation efficiency, large system size, and heavy system weight in existing energy conversion systems based on the traditional Brayton cycle. It provides an energy conversion system and its application. This system can simultaneously meet the requirements of high heat conversion efficiency, high power generation efficiency, and low system size and weight.

[0007] The present invention mainly adopts the following technical solutions to solve the above-mentioned technical problems:

[0008] This invention provides an energy conversion system comprising a three-in-one system, a nuclear reactor, a regenerator, and a precooler;

[0009] The regenerator and the precooler are respectively located on the extended lines at both ends of the axis of the nuclear reactor, and the three-in-one system is located directly above the nuclear reactor;

[0010] The three-in-one system includes a compressor, a generator, and a turbine arranged coaxially, with the generator located between the compressor and the turbine;

[0011] The compressor is used to pressurize helium-xenon gas, and includes a first helium-xenon gas inlet and a first helium-xenon gas outlet;

[0012] The nuclear reactor is used to provide heat to the helium-xenon gas, and includes a second helium-xenon gas inlet and a second helium-xenon gas outlet;

[0013] The turbine includes a third helium-xenon gas inlet and a third helium-xenon gas outlet;

[0014] The regenerator includes a cold fluid channel and a hot fluid channel that exchange heat with each other;

[0015] The first helium-xenon gas outlet is connected to the second helium-xenon gas inlet through the cold fluid channel of the regenerator, and the second helium-xenon gas outlet is connected to the third helium-xenon gas inlet. The third helium-xenon gas outlet, the hot fluid channel of the regenerator, the precooler and the first helium-xenon gas inlet are connected in sequence to form a helium-xenon gas circulation loop.

[0016] Both the regenerator and the precooler are printed circuit board type heat exchangers.

[0017] In this invention, the printed circuit board type heat exchanger preferably includes a heat exchanger core, the heat exchanger core includes a fluid channel plate, the fluid channel plate has a fluid channel, the fluid channel extends from one end of the fluid channel plate to the other end, the inner wall of the fluid channel is provided with a plurality of radially outward protruding fin channels along the extension direction of the fluid channel, the fin channels are in communication with the fluid channel, and the fin channels extend from one end of the fluid channel plate to the other end.

[0018] To meet the system's requirements for higher heat exchange efficiency or pressure drop in the regenerator and precooler, protruding finned channels are added to the fluid channels, increasing the heat exchange area and heat transfer capacity, thereby further improving the compactness of the heat exchanger core. Secondly, the finned channels increase the cross-sectional area of ​​the fluid channels, reducing the flow velocity of the heat exchange medium under the same flow conditions, thus lowering the pressure drop of the heat exchange medium during flow and reducing pump power. Finally, the finned channels can disrupt the flow of the fluid channel boundary layer, causing the heat exchange medium to form a secondary flow in the fluid channels, increasing the disturbance intensity, improving the overall heat transfer coefficient of the heat exchanger core, and improving the heat exchange efficiency of the heat exchanger core.

[0019] The heat exchanger core can be prepared by conventional methods in the art, such as etching heat exchange channels on the heat exchange plate using an etching process, and then using diffusion welding technology to stack and weld the heat exchange plates into a heat exchanger core.

[0020] In this invention, the use of printed circuit board heat exchangers for the precooler and the regenerator can effectively reduce the volume and mass of the precooler and the regenerator, further achieving the goal of reducing the system volume and mass, making it easier to transport and apply.

[0021] In this invention, the connecting pipe between the first helium-xenon gas outlet and the cold fluid channel of the regenerator is preferably composed of at least two pipe segments connected vertically in sequence; the connecting pipe between the third helium-xenon gas outlet and the hot fluid channel of the regenerator is preferably composed of at least two pipe segments connected vertically in sequence; the connecting pipe between the hot fluid channel of the regenerator and the precooler is preferably composed of at least two pipe segments connected vertically in sequence; and the connecting pipe between the precooler and the first helium-xenon gas inlet is preferably composed of at least two pipe segments connected vertically in sequence. Using the above connection method, the boundary layer of the fluid separates due to the inertial force of the fluid, generating eddies, which intensifies the heat exchange between the fluids, thereby enhancing the heat transfer capacity.

[0022] The system of this invention integrates the compressor, generator, and turbine into a single unit, employing a compact coaxial layout. The generator is positioned between the compressor and turbine. This design provides excellent rotor dynamics, overcomes the thrust balance problem of high-pressure fluid turbomachinery, and simplifies the shaft system design. Not placing the generator between the compressor and turbine would complicate the shaft system design.

[0023] This invention uses essential system components such as compressors, generators, turbines, precoolers, and regenerators as shielding bodies, and combines them with a specific arrangement to shield neutrons and photons from the nuclear reactor from both the axial and radial directions. This effectively reduces the size and weight of the system, improves its lightweight nature, safety, and reliability, meets the personnel shielding and radiation protection requirements in mobile application scenarios, and conforms to the design strategy requirements of intelligent shielding systems under multi-objective requirements.

[0024] In this invention, the precooler is preferably also connected to a fan for recovering the heat of the helium-xenon gas; wherein, the number and power of the fan can be determined according to the actual situation, the number of fans can be 3, the power of the fan can be 22kW, and the cold trap of the fan is preferably air.

[0025] In this invention, the height of the nuclear reactor is preferably 0.5-1.5m, for example 1m; the radius of the nuclear reactor is preferably 0.4-0.5m, for example 0.44m.

[0026] In this invention, the nuclear reactor is preferably a high-temperature gas-cooled reactor (HTGR), such as a JIMO reactor, Holos reactor, SIMONS reactor, or Xe-100 reactor. Using an HTGR allows helium-xenon gas to directly absorb the heat transferred from the reactor core, improving heat exchange efficiency; furthermore, an HTGR can provide at least 10 years of power supply without additional refueling, meeting long-term energy needs.

[0027] The JIMO reactor is the JIMO nuclear electric propulsion unit (Jupiter's icy moon orbiter) used in the US Prometheus program. The JIMO reactor power supply has a rated power of 100 kWe, and the thermoelectric conversion section includes two independent 100 kWe Brayton cycle systems, using a He / Xe mixed gas as the working fluid. The Holos reactor integrates a modular power conversion system in each sealed core subassembly, which can be configured to provide a power load of 3-81 MWe, and is plug-and-play, operating 24 / 7.

[0028] The high-temperature gas-cooled reactor generally includes a fuel channel, a coolant channel, and a radial reflector layer. Those skilled in the art can adjust the operating parameters and materials used in the high-temperature gas-cooled reactor according to specific needs. For example, in a specific embodiment of the present invention, the diameter of the fuel channel is 1.5 cm, the diameter of the coolant channel is 0.8 cm, the thickness of the outer shell covering the coolant channel is 0.05 cm, the distance between the fuel channel and the coolant channel is 1.5 cm, and the thickness of the radial reflector layer is 33 cm. The fuel used is uranium carbide (UC) with a U-235 enrichment of 19.75%. The material of the outer shell covering the coolant channel is titanium-zirconium-molybdenum alloy (TZM), the substrate is graphite, and the radial reflector layer uses Be.

[0029] In this invention, based on the cross-sectional area perpendicular to the axis of the nuclear reactor, the axial cross-sectional areas of the regenerator and the precooler preferably cover 50%-100% of the axial cross-sectional area of ​​the nuclear reactor, and more preferably 80%-100%.

[0030] In this invention, the length of the regenerator is preferably 0.7-0.8m, for example 0.78m; the width of the regenerator is preferably 1-2m, for example 1.54m; and the height of the regenerator is preferably 1-2m, for example 1.54m.

[0031] In this invention, the length of the precooler is preferably 0.6-0.65m, for example 0.62m; the width of the precooler is preferably 1-2m, for example 1.54m; and the height of the precooler is preferably 1-2m, for example 1.54m.

[0032] In this invention, the overall height of the three-in-one system is preferably 0.5-1m, for example 0.8m; the overall width is preferably 0.5-1m, for example 0.8m; and the overall length is preferably 2-3m, for example 2.5m.

[0033] In this invention, the diameter of the compressor is preferably 0.5-1.5m, for example 1m; the length of the compressor is preferably 0.3-0.7m, for example 0.5m.

[0034] In this invention, the diameter of the turbine is preferably 0.5-1.5m, for example 1m; and the length of the turbine is preferably 0.3-0.7m, for example 0.5m.

[0035] In this invention, the diameter of the generator is preferably 0.5-1.5m, for example 1m; the length of the generator is preferably 1-3m, for example 2m; and the length of the generator's central shaft is preferably 4-6m, for example 5m.

[0036] In this invention, the shaft support in the three-machine integrated system preferably employs dynamic pressure foil radial bearings and thrust foil bearings. This method can reduce frictional loss, improve circulation efficiency, and ensure the cleanliness of the working fluid.

[0037] In this invention, the compressor, generator, turbine, regenerator, and precooler are preferably all made of nickel-based high-temperature alloy materials. Using nickel-based alloy materials provides resistance to radiation, high temperature, and high pressure, which is more conducive to meeting the system's requirements for personnel shielding and radiation protection in mobile application scenarios.

[0038] In this invention, the energy conversion system generally also includes a shield to meet the system's requirements for personnel shielding and radiation protection in mobile application scenarios.

[0039] This invention provides an application of the above-mentioned energy conversion system, which includes the following steps:

[0040] (1) After being compressed by the compressor, the helium-xenon gas absorbs heat through the cold fluid channel of the regenerator and the nuclear reactor in sequence to obtain helium-xenon gas with high temperature and high pressure.

[0041] (2) The helium-xenon gas with high temperature and high pressure enters the turbine, driving the generator and the compressor to do work, respectively for generating electricity and compressing the helium-xenon gas;

[0042] (3) The helium-xenon gas that has entered the turbine and done work passes through the hot fluid channel of the regenerator and the precooler in sequence and returns to the compressor.

[0043] In this invention, the compressor can be a conventional compressor in the art, and the efficiency of the compressor is preferably 85%-92%, for example 90.3%; the mass of the compressor is preferably 0.1-0.3 tons, for example 0.2 tons.

[0044] In this invention, the pressure of the helium-xenon gas compressed by the compressor is preferably 1500-2500 kPa, for example, 2000 kPa.

[0045] In this invention, the temperature of the helium-xenon gas compressed by the compressor is preferably 400-500K, for example 485.85K.

[0046] In this invention, the pressure of the helium-xenon gas after passing through the cold fluid channel of the regenerator is preferably 1500-2500 kPa, for example 1970 kPa.

[0047] In this invention, the temperature of the helium-xenon gas after passing through the cold fluid channel of the regenerator is preferably 800-900K, for example 925.72K.

[0048] In this invention, the pressure of the helium-xenon gas after passing through the hot fluid channel of the regenerator is preferably 500-1500 kPa, for example 960 kPa.

[0049] In this invention, the temperature of the helium-xenon gas after passing through the hot fluid channel of the regenerator is preferably 400-600K, for example 508.99K.

[0050] In this invention, the efficiency of the regenerator is preferably 90%-98%, for example 95%; the mass of the regenerator is preferably 1-2 tons, for example 1.65 tons.

[0051] In this invention, the pressure of the helium-xenon gas in a high-temperature and high-pressure state is preferably 1500-2000 kPa, for example, 1860 kPa.

[0052] In this invention, the temperature of the helium-xenon gas in a high-temperature and high-pressure state is preferably 1000-2000K, for example, 1200K.

[0053] In this invention, the mass of the nuclear reactor is preferably 4-5 tons, for example 4.9 tons; the thermal power of the nuclear reactor is preferably 15-25MW, for example 20MW.

[0054] In this invention, the pressure of the helium-xenon gas after passing through the turbine is preferably 500-1500 kPa, for example 980 kPa.

[0055] In this invention, the temperature of the helium-xenon gas after passing through the turbine is preferably 500-1000K, for example 948.87K.

[0056] In this invention, the efficiency of the turbine is preferably 90%-95%, for example 92.4%; the mass of the turbine is preferably 0.1-0.5 tons, for example 0.3 tons.

[0057] In this invention, the temperature of the helium-xenon gas after passing through the precooler is preferably 300-400K, for example, 350K.

[0058] In this invention, the pressure of the helium-xenon gas after passing through the precooler is preferably 800-1500 kPa, for example 950 kPa.

[0059] In this invention, the efficiency of the precooler is preferably 70%-90%, for example 79%; the mass of the precooler is preferably 1-2 tons, for example 1.32 tons.

[0060] In this invention, the mass flow rate of the helium-xenon gas is preferably 50-70 kg / s, for example 51.91 kg / s.

[0061] In this invention, the volume of helium in the helium-xenon gas is preferably 80%-90%, for example, 88%.

[0062] This invention utilizes helium-xenon gas. Helium, as a working fluid, offers advantages such as high thermal efficiency, stable chemical properties, and good material compatibility. However, helium's low density results in bulky system piping, and its low specific heat ratio leads to an excessive number of helium compressor and turbine stages, hindering system compactness. The helium-xenon mixture, by adding a certain proportion of xenon, increases the density and specific heat ratio of the circulating working fluid, significantly mitigating the shortcomings of helium and meeting the requirement for system compactness while maintaining thermal efficiency.

[0063] In a preferred embodiment of the present invention, the nuclear reactor satisfies the following conditions:

[0064]

[0065]

[0066] Based on common knowledge in the field, the above-mentioned preferred conditions can be combined arbitrarily to obtain various preferred embodiments of the present invention.

[0067] The working fluid, reagents and raw materials used in this invention are all commercially available.

[0068] The positive and progressive effects of this invention are as follows:

[0069] The system of this invention integrates the compressor, generator and turbine into one unit, adopts a compact coaxial layout, has good rotor dynamic characteristics, can overcome the thrust balance problem of high pressure fluid turbomachinery, and has a simple shaft system design. By using the essential equipment of the system as a shield and combining it with a specific arrangement, the size and weight of the system can be effectively reduced, the system's lightweightness, safety and reliability can be improved, and the requirements for personnel shielding and radiation protection in mobile application scenarios can be met.

[0070] This invention adds a regenerator to the traditional Brayton cycle system, giving it high cycle efficiency, high thermoelectric conversion efficiency, and high electrical power. Attached Figure Description

[0071] Figure 1 This is a schematic diagram of the energy conversion system in Example 1.

[0072] Figure 2 This is a schematic diagram of the energy conversion system in Comparative Example 1.

[0073] Figure 3 This is a schematic diagram of the energy conversion system in Comparative Example 2.

[0074] Figure 4 This is a schematic diagram of the energy conversion system in Comparative Example 3.

[0075] The annotations in the attached figures are explained as follows:

[0076] 1-Compressor; 2-Regenerator; 201-Third Pipe; 202-Sixth Pipe; 3-Nuclear Reactor; 301-Fourth Pipe; 4-Turbine; 401-Fifth Pipe; 5-Precooler; 501-First Pipe; 6-Generator; 7-Fan; 8-Carriage; 9-First Compressor; 901-Second Pipe; 10-Second Compressor; 1001-Eighth Pipe; 11-Intercooler; 1101-Seventh Pipe; 12-First Regenerator; 13-Second Regenerator. Detailed Implementation

[0077] The present invention is further illustrated below by way of embodiments, but the invention is not limited to the scope of the embodiments described herein. Experimental methods in the following embodiments that do not specify specific conditions were performed according to conventional methods and conditions, or as selected according to the product instructions.

[0078] Example 1

[0079] The schematic diagram of the energy conversion system used in this embodiment is shown below. Figure 1 As shown. It includes a three-in-one system, a nuclear reactor 3, a regenerator 2, and a precooler 5;

[0080] The regenerator 2 and the precooler 5 are respectively located on the extended lines at both ends of the axis of the nuclear reactor 3, and the three-in-one system is located directly above the nuclear reactor 3;

[0081] The three-in-one system includes a compressor 1, a generator 6, and a turbine 4 arranged coaxially, with the generator 6 located between the compressor 1 and the turbine 4;

[0082] Compressor 1 is used to pressurize helium-xenon gas, and it includes a first helium-xenon gas inlet and a first helium-xenon gas outlet;

[0083] Nuclear reactor 3 is used to provide heat to helium-xenon gas, and it includes a second helium-xenon gas inlet and a second helium-xenon gas outlet;

[0084] Turbine 4 includes a third helium-xenon gas inlet and a third helium-xenon gas outlet;

[0085] The regenerator 2 includes a cold fluid channel and a hot fluid channel that exchange heat with each other;

[0086] The first helium-xenon gas outlet is connected to the second helium-xenon gas inlet through the cold fluid channel of the regenerator 2. The second helium-xenon gas outlet is connected to the third helium-xenon gas inlet. The third helium-xenon gas outlet, the hot fluid channel of the regenerator 2, the precooler 5, and the first helium-xenon gas inlet are connected in sequence to form a helium-xenon gas circulation loop.

[0087] Nuclear reactor 3 is a high-temperature gas-cooled reactor, which meets the conditions in Table 1 below:

[0088] Table 1

[0089] Model of nuclear reactor 3 SIMONS reactor Thermal power MW 20 Full power operating time days 3300 Reactivity control method Pulling reflector System pressure MPa 2.3 Volume fraction of helium gas % 88 Mass flow of helium-xenon gas kg / s 62 Temperature of helium-xenon gas after the cold fluid passage of the recuperator 2 K 914 Temperature of helium-xenon gas with high temperature and high pressure K 1200 Mass of nuclear reactor 3 tons 4.9 Diameter of fuel channel cm 1.5 Diameter of coolant channel cm 0.8 Thickness of outer cladding of coolant channel cm 0.05 Spacing between fuel channel and coolant channel cm 1.5 Thickness of radial reflector cm 33 Number of fuel rods in nuclear reactor 3 1040 Radius of nuclear reactor 3 cm 44 Height of nuclear reactor 3 cm 100 Fuel UC Enrichment of U-235 % 19.75 Outer cladding material of coolant channel TZM Matrix material Graphite Radial reflector material Be

[0090] The compressor 1, regenerator 2, nuclear reactor 3, turbine 4, precooler 5, generator 6, and fan 7 are all placed inside the carriage 8.

[0091] The wind turbine 7 uses three 22kW units with impeller diameters of 1.5m.

[0092] This embodiment includes the following steps:

[0093] (1) After being compressed by compressor 1, helium-xenon gas absorbs heat through the cold fluid channel of regenerator 2 and nuclear reactor 3 in sequence to obtain helium-xenon gas with high temperature and high pressure.

[0094] (2) Helium-xenon gas with high temperature and high pressure enters turbine 4, driving generator 6 and compressor 1 to do work, which is used for power generation and compression of helium-xenon gas respectively.

[0095] (3) The helium-xenon gas that has done work in turbine 4 returns to compressor 1 through the hot fluid channel of regenerator 2 and precooler 5 in sequence;

[0096] (4) Repeat steps (1)-(3).

[0097] The specific process parameters are listed in Table 2 below:

[0098] Table 2

[0099]

[0100]

[0101]

[0102] Comparative Example 1

[0103] The schematic diagram of the energy conversion system used in Comparative Example 1 is shown below. Figure 2 As shown. It includes a first compressor 9, a second compressor 10, a turbine 4, a generator 6, a precooler 5, a nuclear reactor 3, a regenerator 2, and an intercooler 11;

[0104] The first compressor 9 and the second compressor 10 are used to pressurize the helium-xenon gas. An intercooler 11 is provided between the first compressor 9 and the second compressor 10. The first compressor 9, the second compressor 10, the turbine 4, and the generator 6 are arranged coaxially in sequence. The nuclear reactor 3 is used to provide heat to the helium-xenon gas. The nuclear reactor 3 is a high-temperature gas-cooled reactor, which meets the conditions in Table 1.

[0105] Comparative Example 1 uses an intercooling cycle energy conversion system, which includes the following steps:

[0106] (1) Helium-xenon gas is compressed sequentially by the first compressor 9, the intercooler 11, and the second compressor 10, and then absorbs heat sequentially by the regenerator 2 and the nuclear reactor 3 to obtain helium-xenon gas with high temperature and high pressure.

[0107] (2) Helium-xenon gas with high temperature and high pressure enters turbine 4 and drives generator 6 to generate electricity;

[0108] (3) The helium-xenon gas that has done work in turbine 4 passes through regenerator 2 and precooler 5 in sequence and returns to the first compressor 9.

[0109] The dimensions and weight of the equipment are listed in Table 3 below, and the process parameters of each pipe in the intercooling cycle are listed in Table 4 below.

[0110] Table 3

[0111]

[0112]

[0113] Table 4

[0114] Temperature K Pressure MPa First pipe 501 350.0 0.79 Second pipe 901 442.56 1.35 Third pipe 201 864.59 1.97 Fourth pipe 301 1200.0 1.86 Fifth pipe 401 886.80 0.82 Sixth pipe 202 464.77 0.80 Seventh pipe 1101 350.0 1.33 Eighth pipe 1001 418.64 2.0

[0115] Comparative Example 2

[0116] A schematic diagram of the energy conversion system used in Comparative Example 2 is shown below. Figure 3 As shown. It includes a first compressor 9, a second compressor 10, a turbine 4, a generator 6, a precooler 5, a nuclear reactor 3, a first regenerator 12, and a second regenerator 13;

[0117] The first compressor 9 and the second compressor 10 are used to pressurize the helium-xenon gas. The first compressor 9, the second compressor 10, the turbine 4, and the generator 6 are arranged coaxially in sequence. The nuclear reactor 3 is used to provide heat to the helium-xenon gas. The nuclear reactor 3 is a high-temperature gas-cooled reactor, which meets the conditions in Table 1.

[0118] Comparative Example 2 uses a recompression cycle energy conversion system, which includes the following steps:

[0119] (1) Helium-xenon gas is sequentially passed through the first compressor 9, the first regenerator 12, the second regenerator 13, and the nuclear reactor 3 to absorb heat and obtain helium-xenon gas with high temperature and high pressure.

[0120] (2) Helium-xenon gas with high temperature and high pressure enters turbine 4 and drives generator 6 to do work for power generation.

[0121] (3) After the helium-xenon gas enters the turbine 4 and does work, it is divided into two parts after passing through the first regenerator 12 and the second regenerator 13. One part returns to the first compressor 9 after passing through the precooler 5, and the other part enters the second regenerator 13 after passing through the second compressor 10.

[0122] The dimensions and mass of the equipment are listed in Table 5 below, and the process parameters of each pipeline in the recompression cycle are listed in Table 6 below.

[0123] Table 5

[0124]

[0125] Table 6

[0126]

[0127]

[0128] Comparative Example 3

[0129] Based on Example 1, without the regenerator, everything else is the same as in Example 1. The schematic diagram of the energy conversion system of Comparative Example 3 is shown below. Figure 4 .

[0130] Example 1

[0131] The equipment in Example 1 can be housed in a 17.5m × 3m × 2.72m van. Key equipment includes a three-in-one system, a nuclear reactor, a regenerator, and a precooler. The total mass of the key equipment is 9.47 tons, the shielding mass is 12.4 tons, and the total mass of the system is 21.87 tons. The energy conversion system of Example 1 has an electrical power output of 8-10MW and a thermoelectric conversion efficiency of 40%.

[0132] The equipment in Example 2 can be housed in a 17.5m × 3m × 2.72m van. The total mass of the key equipment is 9.47 tons, the shielding body is 15.7 tons, and the total mass of the system is 25.17 tons. The helium-xenon gas energy conversion system in Example 2 has an electrical power of 8-10MW and a thermoelectric conversion efficiency of 40%.

[0133] The equipment in Example 3 can be placed in a van measuring 18.5m × 4m × 3.72m. The total mass of the key equipment is 9.47 tons, the shielding body is 18.6 tons, and the total mass of the system is 28.07 tons. The helium-xenon gas energy conversion system in Example 1 has an electrical power of 8-10MW and a thermoelectric conversion efficiency of 40%.

[0134] The thermoelectric conversion efficiency of Comparative Example 1 is 44%, the power of the energy conversion system can reach 8-10MW, the total mass of the key equipment is 14.34 tons, the mass of the shielding body is 18.6 tons, and the total mass of the system is 32.94 tons.

[0135] Comparative Example 2 has a thermoelectric conversion efficiency of 41%, an energy conversion system power of 8-10MW, a total mass of 18.32 tons for key equipment, a shielding mass of 18.6 tons, and a total system mass of 36.92 tons.

[0136] The thermoelectric conversion efficiency of Comparative Example 3 is 17.04%, the power of the energy conversion system can reach 8-10MW, the total mass of the key equipment is 7.31 tons, the mass of the shielding body is 18.6 tons, and the total mass of the system is 25.91 tons.

[0137] The energy conversion system of the present invention employs a Brayton cycle, which has significant advantages in quality compared with Comparative Examples 1 and 2, and can also achieve higher cycle efficiency.

[0138] In Examples 1-3, with identical process parameters, thermoelectric conversion efficiency, and electrical power, Example 1 reduced the shield mass to 12.4 tons when the total mass of the key equipment was consistent, by adjusting the position and arrangement of the key equipment so that the axial cross-sectional area of ​​the regenerator and precooler covered 100% of the axial cross-sectional area of ​​the nuclear reactor. This effectively reduced the total mass of the system.

[0139] In other alternative implementations, the size of the Brayton cycle system equipment can be further adjusted to meet different usage requirements and adapt reasonably to various usage scenarios.

[0140] In the description of this invention, it should be understood that the terms "upper", "lower", "front", "rear", "left", "right", "vertical", "horizontal", "top", "bottom", "inner", "outer", etc., indicate the orientation or positional relationship based on the orientation or positional relationship shown in the accompanying drawings. They are only for the convenience of describing this invention and simplifying the description, and do not indicate or imply that the device or element referred to must have a specific orientation, or be constructed and operated in a specific orientation. Therefore, they should not be construed as limitations on this invention.

[0141] While specific embodiments of the present invention have been described above, those skilled in the art should understand that these are merely illustrative examples, and the scope of protection of the present invention is defined by the appended claims. Those skilled in the art can make various changes or modifications to these embodiments without departing from the principles and essence of the present invention, but all such changes and modifications fall within the scope of protection of the present invention.

Claims

1. An energy conversion system, characterized in that, It includes a three-in-one system, a nuclear reactor, a regenerator, and a precooler; The regenerator and the precooler are respectively located on the extended lines at both ends of the axis of the nuclear reactor, and the three-in-one system is located directly above the nuclear reactor; The three-in-one system includes a compressor, a generator, and a turbine arranged coaxially, with the generator located between the compressor and the turbine; The compressor is used to pressurize helium-xenon gas, and includes a first helium-xenon gas inlet and a first helium-xenon gas outlet; The nuclear reactor is used to provide heat to the helium-xenon gas, and includes a second helium-xenon gas inlet and a second helium-xenon gas outlet; The turbine includes a third helium-xenon gas inlet and a third helium-xenon gas outlet; The regenerator includes a cold fluid channel and a hot fluid channel that exchange heat with each other; The first helium-xenon gas outlet is connected to the second helium-xenon gas inlet through the cold fluid channel of the regenerator, and the second helium-xenon gas outlet is connected to the third helium-xenon gas inlet. The third helium-xenon gas outlet, the hot fluid channel of the regenerator, the precooler and the first helium-xenon gas inlet are connected in sequence to form a helium-xenon gas circulation loop. Both the regenerator and the precooler are printed circuit board type heat exchangers; Based on the cross-sectional area perpendicular to the axis of the nuclear reactor, the axial cross-sectional areas of the regenerator and the precooler cover 50%-100% of the axial cross-sectional area of ​​the nuclear reactor.

2. The energy conversion system as described in claim 1, characterized in that, The printed circuit board type heat exchanger includes a heat exchanger core, the heat exchanger core includes a fluid channel plate, the fluid channel plate has a fluid channel, the fluid channel extends from one end of the fluid channel plate to the other end, the inner wall of the fluid channel is provided with a plurality of radially outward protruding fin channels along the extension direction of the fluid channel, the fin channels are in communication with the fluid channel, and the fin channels extend from one end of the fluid channel plate to the other end.

3. The energy conversion system as described in claim 1, characterized in that, The connecting pipe between the first helium-xenon gas outlet and the cold fluid channel of the regenerator consists of at least two pipe segments connected vertically in sequence; the connecting pipe between the third helium-xenon gas outlet and the hot fluid channel of the regenerator consists of at least two pipe segments connected vertically in sequence; the connecting pipe between the hot fluid channel of the regenerator and the precooler consists of at least two pipe segments connected vertically in sequence; and the connecting pipe between the precooler and the first helium-xenon gas inlet consists of at least two pipe segments connected vertically in sequence. And / or, the precooler is also connected to a fan for recovering the heat from the helium-xenon gas; And / or, the nuclear reactor is a high-temperature gas-cooled reactor.

4. The energy conversion system as described in claim 1, characterized in that, The axial cross-sectional area of ​​the regenerator and the precooler covers 80%-100% of the axial cross-sectional area of ​​the nuclear reactor.

5. The energy conversion system as described in claim 1, characterized in that, The length of the regenerator is 0.7-0.8m; the width of the regenerator is 1-2m; the height of the regenerator is 1-2m. And / or, the length of the precooler is 0.6-0.65m; the width of the precooler is 1-2m; the height of the precooler is 1-2m; And / or, the height of the nuclear reactor is 0.5-1.5m; the radius of the nuclear reactor is 0.4-0.5m; And / or, the overall height of the three-in-one system is 0.5-1m; Overall width is 0.5-1m; overall length is 2-3m; And / or, the diameter of the compressor is 0.5-1.5m; the length of the compressor is 0.3-0.7m; And / or, the diameter of the turbine is 0.5-1.5m; the length of the turbine is 0.3-0.7m; And / or, the diameter of the generator is 0.5-1.5m; the length of the generator is 1-3m; the length of the generator's central shaft is 4-6m.

6. The energy conversion system as described in claim 5, characterized in that, The length of the regenerator is 0.78m.

7. The energy conversion system as described in claim 5, characterized in that, The width of the regenerator is 1.54m.

8. The energy conversion system as described in claim 5, characterized in that, The height of the regenerator is 1.54m.

9. The energy conversion system as described in claim 5, characterized in that, The precooler is 0.62m long.

10. The energy conversion system as described in claim 5, characterized in that, The width of the precooler is 1.54m.

11. The energy conversion system as described in claim 5, characterized in that, The height of the precooler is 1.54m.

12. The energy conversion system as described in claim 5, characterized in that, The height of the nuclear reactor is 1m.

13. The energy conversion system as described in claim 5, characterized in that, The radius of the nuclear reactor is 0.44m.

14. The energy conversion system as described in claim 5, characterized in that, The overall height of the three-in-one system is 0.8m.

15. The energy conversion system as described in claim 5, characterized in that, The overall width of the three-in-one system is 0.8m.

16. The energy conversion system as described in claim 5, characterized in that, The overall length of the three-in-one system is 2.5m.

17. The energy conversion system as described in claim 5, characterized in that, The compressor has a diameter of 1m.

18. The energy conversion system as described in claim 5, characterized in that, The compressor is 0.5m long.

19. The energy conversion system as described in claim 5, characterized in that, The turbine has a diameter of 1m.

20. The energy conversion system as described in claim 5, characterized in that, The turbine is 0.5m long.

21. The energy conversion system as described in claim 5, characterized in that, The generator has a diameter of 1m.

22. The energy conversion system as described in claim 5, characterized in that, The generator is 2m long.

23. The energy conversion system as described in claim 5, characterized in that, The generator's central shaft is 5m long.

24. The energy conversion system as described in claim 1, characterized in that, The compressor has a mass of 0.1-0.3 tons; And / or, the turbine has a mass of 0.1-0.5 tons; And / or, the mass of the regenerator is 1-2 tons; And / or, the mass of the nuclear reactor is 4-5 tons; And / or, the mass of the precooler is 1-2 tons.

25. The energy conversion system as described in claim 24, characterized in that, The compressor has a mass of 0.2 tons.

26. The energy conversion system as described in claim 24, characterized in that, The turbine has a mass of 0.3 tons.

27. The energy conversion system as described in claim 24, characterized in that, The regenerator has a mass of 1.65 tons.

28. The energy conversion system as described in claim 24, characterized in that, The nuclear reactor has a mass of 4.9 tons.

29. The energy conversion system as described in claim 24, characterized in that, The precooler has a mass of 1.32 tons.

30. The energy conversion system as described in claim 1, characterized in that, The shaft support in the three-machine integrated system adopts dynamic pressure foil radial bearings and thrust foil bearings; And / or, the compressor, the generator, the turbine, the regenerator, and the precooler are all made of nickel-based high-temperature alloy materials.

31. The application of the energy conversion system as described in any one of claims 1-30, characterized in that, It includes the following steps: (1) After being compressed by the compressor, the helium-xenon gas absorbs heat through the cold fluid channel of the regenerator and the nuclear reactor in sequence to obtain helium-xenon gas with high temperature and high pressure. (2) The helium-xenon gas with high temperature and high pressure enters the turbine, driving the generator and the compressor to do work, respectively for generating electricity and compressing the helium-xenon gas; (3) The helium-xenon gas that has done work in the turbine passes through the hot fluid channel of the regenerator and the precooler in sequence and returns to the compressor; (4) Repeat steps (1)-(3).

32. The application of the energy conversion system as described in claim 31, characterized in that, The compressor has an efficiency of 85%-92%; And / or, the pressure of the helium-xenon gas compressed by the compressor is 1500-2500 kPa; And / or, the pressure of the helium-xenon gas after passing through the cold fluid passage of the regenerator is 1500-2500 kPa; the temperature of the helium-xenon gas after being compressed by the compressor is 400-500 K; And / or, the pressure of the helium-xenon gas in the high-temperature and high-pressure state is 1500-2500 kPa; the temperature of the helium-xenon gas in the high-temperature and high-pressure state is 1000-2000 K; And / or, the pressure of the helium-xenon gas after passing through the turbine is 500-1500 kPa; the temperature of the helium-xenon gas after passing through the turbine is 500-1000 K; and the efficiency of the turbine is 90%-95%. And / or, the pressure of the helium-xenon gas after passing through the hot fluid channel of the regenerator is 500-1500 kPa; the temperature of the helium-xenon gas after passing through the hot fluid channel of the regenerator is 400-600 K; And / or, the temperature of the helium-xenon gas after passing through the precooler is 300-400K; the pressure of the helium-xenon gas after passing through the precooler is 800-1500kPa; and the efficiency of the precooler is 70%-90%.

33. The application of the energy conversion system as described in claim 32, characterized in that, The compressor has an efficiency of 90.3%.

34. The application of the energy conversion system as described in claim 32, characterized in that, The pressure of the helium-xenon gas after being compressed by the compressor is 2000 kPa.

35. The application of the energy conversion system as described in claim 32, characterized in that, The pressure of the helium-xenon gas after passing through the cold fluid channel of the regenerator is 1970 kPa.

36. The application of the energy conversion system as described in claim 32, characterized in that, The temperature of the helium-xenon gas after being compressed by the compressor is 485.85K.

37. The application of the energy conversion system as described in claim 32, characterized in that, The pressure of the helium-xenon gas, which is in a high-temperature and high-pressure state, is 1860 kPa.

38. The application of the energy conversion system as described in claim 32, characterized in that, The temperature of the helium-xenon gas, which is under high temperature and high pressure, is 1200K.

39. The application of the energy conversion system as described in claim 32, characterized in that, The pressure of the helium-xenon gas after passing through the turbine is 980 kPa.

40. The application of the energy conversion system as described in claim 32, characterized in that, The temperature of the helium-xenon gas after passing through the turbine is 948.87 K.

41. The application of the energy conversion system as described in claim 32, characterized in that, The turbine has an efficiency of 92.4%.

42. The application of the energy conversion system as described in claim 32, characterized in that, The pressure of the helium-xenon gas after passing through the hot fluid channel of the regenerator is 960 kPa.

43. The application of the energy conversion system as described in claim 32, characterized in that, The temperature of the helium-xenon gas after passing through the hot fluid channel of the regenerator is 508.99K.

44. The application of the energy conversion system as described in claim 32, characterized in that, The temperature of the helium-xenon gas after passing through the precooler is 350K.

45. The application of the energy conversion system as described in claim 32, characterized in that, The pressure of the helium-xenon gas after passing through the precooler is 950 kPa.

46. ​​The application of the energy conversion system as described in claim 32, characterized in that, The efficiency of the precooler is 79%.

47. The application of the energy conversion system as described in claim 31, characterized in that, The mass flow rate of the helium-xenon gas is 50-70 kg / s; And / or, in the helium-xenon gas, the volume percentage of helium is 80%-90%.

48. The application of the energy conversion system as described in claim 47, characterized in that, The mass flow rate of the helium-xenon gas is 51.91 kg / s.

49. The application of the energy conversion system as described in claim 47, characterized in that, In the helium-xenon gas, helium accounts for 88% of the volume.

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