CN116682581A

CN116682581A - Gas cooled reactor and combined system of gas cooled reactor and fusion reactor

Info

Publication number: CN116682581A
Application number: CN202310826382.2A
Authority: CN
Inventors: 田英男; 米爱军; 李晓静; 常叶笛; 胡小利; 王晓霞; 王炳衡; 申静怡; 谢思洋; 高桂玲; 王晓亮; 邱林; 赵秋娟; 朱宇琛; 李璐; 邵增; 陈添
Original assignee: China Nuclear Power Engineering Co Ltd
Current assignee: China Nuclear Power Engineering Co Ltd
Priority date: 2023-07-06
Filing date: 2023-07-06
Publication date: 2023-09-01

Abstract

The invention discloses a gas cooled reactor capable of producing tritium and a combined system of the gas cooled reactor and a fusion reactor; the gas-cooled reactor comprises a reactor core, a nuclear fuel sealing isolation layer and a reactor pressure container which are arranged from inside to outside along the radial direction of the gas-cooled reactor, and further comprises a tritium production module system, wherein the tritium production module system is positioned at the periphery of the reactor core and between the nuclear fuel sealing isolation layer and the reactor pressure container, and comprises tritium proliferation materials, and the tritium proliferation materials react with neutrons generated by the reactor core to generate tritium elements. The radiation hazard of the neutron leakage of the gas cooled reactor high reactor core to the reactor components, external personnel and equipment can be solved, and the thicknesses of the gas cooled reactor reflecting layer, the moderating layer and the external shielding body 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 for the fusion reactor so as to solve the problems of tritium self-holding and fuel supplementation of the fusion reactor.

Description

Gas cooled reactor and combined system of gas cooled reactor and fusion reactor

Technical Field

The invention relates to the technical field of reactors, in particular to a gas cooled reactor and a combined system of the gas cooled reactor and a fusion reactor.

Background

At present, the main purposes of research and design of the gas cooled reactor at home and abroad include nuclear power generation, power supply, hydrogen production and the like. The gas cooled reactor has higher proportion of high-energy neutrons, has higher core neutron leakage rate and harder neutron energy spectrum than the water cooled reactor, needs more fuel loading capacity, higher enrichment degree of easily-cracked nuclides, and brings a harsher neutron irradiation environment. Neutrons leaking from the core, especially fast neutrons with energies above 0.1MeV and 1.0MeV, will affect the mechanical properties of the devices such as reactor internals, pressure vessels, etc., except for irradiation damage to these devices, and as the cumulative neutron fluence increases. Therefore, key equipment such as the pressure vessel and the like can age more quickly, and the important safety risks of embrittlement, fracture and failure of the equipment are greatly increased. At the same time, neutrons leaking from the reactor core of the gas cooled reactor will also increase the radiation level outside the reactor, bringing irradiation risks to external personnel and equipment. Thus, it is necessary to provide neutron moderating and reflecting materials such as graphite at the core or core periphery of the gas cooled reactor, or to increase the thickness of the shield or to use materials with stronger shielding properties outside the reactor, but these measures will greatly increase the volume, mass and cost of the gas cooled reactor. If a functional component for tritium production is arranged in the gas cooled reactor, the problems can be well solved.

In addition, a major difficulty faced by fusion stacks and fusion fission hybrid stacks designed at home and abroad is tritium self-sustaining. The tritium proliferation ratio (TBR) analysis value of each engineering experimental fusion reactor or fusion fission mixed reactor which is currently designed and developed is below 1.2 (inclusive), and the fusion fission mixed reactor is generally lower than the fusion reactor. In fact, tritium at high temperatures can permeate out of the barrier of the tritium collection system, causing a percentage of the loss. Meanwhile, the collection, purification and treatment of tritium are difficult to reach theoretical analysis and design level under the current state of the art. In addition to the above factors, the loss of tritium during storage and treatment is considered, so that the engineering is difficult to realize true 'tritium self-sustaining' in practice.

The prior art CN103578579a discloses a loading scheme for fusion-fission subcritical energy reactor cores. The reactor core structure comprises a plurality of fuel assembly modules which are arranged along the circumferential direction of an annular plasma fusion zone, each fuel assembly module comprises a plurality of fuel assemblies which are arranged in the polar direction of the plasma fusion zone, a layer of high-temperature resistant and irradiation resistant first wall is arranged on one side, facing the plasma fusion zone, of each fuel assembly, a tritium producing cladding is arranged on the other side, opposite to the first wall, of each fuel assembly, and an outer shielding is arranged outside the tritium producing cladding.

The prior art CN103578574A discloses a fusion-fission subcritical energy reactor core tritium production cladding, which comprises a plurality of layers of tritium production materials, wherein moderator water is arranged between two adjacent layers of tritium production materials, a zirconium partition plate is arranged between the tritium production materials and the moderator water, and a zirconium cladding is arranged outside the tritium production cladding.

The design of the prior art can not realize better tritium producing effect of the gas-cooled reactor, enhance the tritium carrying capacity of the gas medium in the gas-cooled reactor, and can not better solve the tritium self-sustaining problem of the fusion reactor and the fusion fission mixed reactor.

In view of the above technical problems, the present invention is particularly directed.

Disclosure of Invention

The invention mainly aims to provide a gas-cooled reactor and a combined system of the gas-cooled reactor and a fusion reactor, which are used for realizing a better tritium production effect of the gas-cooled reactor, enhancing the tritium carrying capacity of a gas medium in the gas-cooled reactor, and solving the tritium self-sustaining problem of the fusion reactor through the combined system.

In order to achieve the above object, according to one aspect of the present invention, there is provided a gas cooled reactor, comprising a reactor core, a nuclear fuel seal isolation layer and a reactor pressure vessel disposed from inside to outside along a radial direction of the gas cooled reactor, and further comprising a tritium producing module system located at a periphery of the reactor core and located between the nuclear fuel seal isolation layer and the reactor pressure vessel, the tritium producing module system comprising tritium proliferation material, the tritium proliferation material reacting with neutrons generated by the reactor core to produce tritium elements.

Further, the gas cooled reactor comprises a reactor coolant inlet, a first gas accelerating device is arranged at the reactor coolant inlet, and a gas medium physical parameter adjusting system is arranged on the first gas accelerating device.

Further, the gas medium physical parameter adjusting system comprises a plurality of connecting pipelines and a valve assembly, a plurality of holes are formed in the wall surface of the air inlet section of the first gas accelerating device and are respectively communicated with the plurality of connecting pipelines, the valve assembly is arranged on the plurality of connecting pipelines, and the valve assembly comprises an adjusting valve, a constant pressure check valve and/or a pressure variable check valve.

Further, the reactor coolant inlet is respectively communicated with the reactor core and the tritium production module system, the gas cooled reactor comprises a splitter plate, the splitter plate is positioned between the first gas accelerating device and the reactor core and also positioned between the first gas accelerating device and the tritium production module system, and the splitter plate isolates the reactor coolant entering the reactor core from the reactor coolant entering the tritium production module system.

Further, the tritium producing module system comprises a tritium producing module system coolant inlet, and the tritium producing module system coolant inlet is provided with a second gas accelerating device; and adjusting the air inflow and parameters of the reactor coolant entering the second gas accelerating device by adjusting the space between the flow dividing plate and the reactor pressure vessel, wherein the reactor coolant entering the tritium producing module system is coupled with the second gas accelerating device.

Further, the first gas accelerating device and/or the second gas accelerating device has a structure with a variable sectional area, and the structure comprises a contraction section, or a contraction section, a narrow throat section and an expansion section which are sequentially connected along the gas flowing direction, wherein the sectional area of the contraction section is changed from large to small along the flowing direction, and the sectional area of the expansion section is changed from small to large along the flowing direction.

Further, the tritium-producing module system further comprises cladding and tritium-producing layer groups, the cladding is arranged at intervals along the radial direction of the gas cooled reactor, the tritium-producing layer groups are arranged between the cladding, the tritium-producing layer groups comprise tritium proliferation layers and/or tritium proliferation multiplication layers, the tritium proliferation layers and the tritium proliferation multiplication layers comprise tritium-producing areas, and the tritium-producing areas comprise tritium proliferation materials.

Further, the tritium-producing layer group further comprises a tritium pipeline for circulating a reactor coolant and a tritium-containing medium, wherein the tritium pipeline extends along the axial direction of the gas cooled reactor, and a plurality of holes are formed in the pipe wall of the tritium pipeline, so that the inside of the tritium pipeline is in fluid communication with the tritium-producing region.

Further, the tritium producing layer group comprises a first neutron multiplication layer and a tritium multiplication layer which are arranged along the radial direction of the gas cooled reactor, the tritium multiplication layer is positioned on the outer side of the first neutron multiplication layer, the first neutron multiplication layer comprises neutron multiplication materials, and the tritium pipeline is at least partially positioned in the tritium multiplication layer.

Further, the tritium-producing module system also comprises a partition board, wherein the partition board is arranged between different types of layers in the tritium-producing layer group and/or between the tritium-producing layer group and other layers; the tritium-producing module system further comprises a tritium-preventing permeation layer, the tritium-preventing permeation layer is adjacent to the cladding, the tritium-preventing permeation layer comprises oxide and titanium-containing ceramic, and the oxide comprises one or more of the following substances: cr (Cr) ₂ O ₃ 、Al ₂ O ₃ 、Ti ₂ O ₂ 。

Further, the tritium producing module system also comprises a radiation product production layer, wherein the material of the radiation product production layer comprises 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 two sides of the irradiation product production layer are provided with partition plates, and the irradiation product production layer is positioned at the outer side of the tritium proliferation layer.

Further, the tritium-producing module system further comprises a first reflecting layer or a first slowing layer, wherein the first reflecting layer or the first slowing layer is positioned outside the production layer of the irradiation product, and the material of the first reflecting layer or the first slowing layer 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.

Further, the tritium-producing layer group comprises a tritium multiplication layer, the tritium multiplication layer comprises a neutron multiplication part and a cylindrical tritium multiplication part, a plurality of tritium multiplication parts are uniformly arranged in the neutron multiplication part, the volume ratio of the neutron multiplication part to the tritium multiplication part is in the range of 2:1 to 8:1, and tritium pipelines are arranged in an array in the tritium multiplication part.

Further, the core comprises a fuel assembly which is divided into a plurality of sections along the axial direction of the gas cooled reactor, and the enrichment degree of the fissionable nuclide of the fuel assembly is increased section by section from the gas inlet end to the gas outlet end of the fuel assembly.

Further, the fuel assembly is divided into 3-8 sections along the axial direction of the gas cooled reactor, and the multi-section fuel assembly adopts fuels of 3-4 fissionable nuclides with different enrichment degrees.

Further, the fuel assembly comprises a fuel assembly coolant flow passage, a third gas accelerating device is arranged on the fuel assembly coolant flow passage, and the third gas accelerating device adopts a structure with a variable sectional area and comprises a contraction section or a contraction section, a narrow throat section and an expansion section which are sequentially connected along the gas circulation direction.

Further, the whole fuel assembly is cylindrical and is divided into multiple layers along the radial direction of the gas cooled reactor, the coolant flow channels of the fuel assembly comprise interlayer flow channels, and the interlayer flow channels are gaps of 2-20 mm between different layers of fuel assemblies; the fuel assembly is further divided into a plurality of sectors along the circumferential direction of the gas cooled stack such that each layer of fuel assembly has a plurality of fuel elements, the fuel assembly coolant flow passage further includes axial channels, and each fuel element has a plurality of axial channels along the axial direction of the gas cooled stack.

Further, the number of axial passages per fuel element is determined according to the following equation:wherein n is the number of axial pore channels, θ is the central angle of the sector where the fuel element is located, and m is the number of layers where the fuel element is located in the radial direction of the gas cooled reactor from inside to outside.

Further, the gas cooled reactor is a high flux gas cooled reactor or a high flux gas cooled fast reactor, and the thermal neutron fluence rate of the tritium producing module system of the high flux gas cooled reactor is 1.0 multiplied by 10 ¹¹ ～5.0×10 ¹⁵ n/cm ² S, the fast neutron fluence rate is 1.5X10 ¹⁰ ～1.0×10 ¹⁵ n/cm ² S; the thermal neutron fluence rate of the tritium-producing module system of the high flux gas cooled fast reactor is 1.0 multiplied by 10 ¹¹ ～5.0×10 ¹⁵ n/cm ² S, the fast neutron fluence rate is 3X 10 ¹² ～5.0×10 ¹⁵ n/cm ² ·s。

Furthermore, the high-flux gas cooled reactor and the high-flux gas cooled fast reactor adopt uranium fuel or uranium thorium MOX fuel, wherein the enrichment degree of U-235 is not lower than 15%; if uranium plutonium MOX fuel, thorium plutonium MOX fuel or uranium thorium plutonium MOX fuel is used, the enrichment degree of Pu-239 is not less than 10%.

Further, 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; and a coolant flow passage and/or a third neutron multiplication layer and/or a third reflection layer and/or a third slowing layer are arranged between the reactor pressure vessel and the tritium production module system.

Further, the nuclear fuel seal isolation layer comprises a metal container or a coaming, and further comprises a fixed supporting member, wherein a neutron adjusting layer is arranged between the reactor core and the nuclear fuel seal isolation layer, the neutron adjusting layer comprises a coolant runner, and/or a fourth neutron multiplying layer and/or a fourth reflecting layer and/or a fourth slowing layer.

Further, the thermal neutron fluence rate of the tritium-producing module system of the gas cooled reactor is 1.0 multiplied by 10 ¹⁰ ～2.0×10 ¹³ n/cm ² S, the fast neutron fluence rate is 5.0X10 ⁹ ～5.0×10 ¹² n/cm ² S; if the gas cooled reactor is a gas cooled fast reactor, the thermal neutron fluence rate of the tritium production module system is 1.0 multiplied by 10 ¹⁰ ～2.0×10 ¹³ n/cm ² S, the fast neutron fluence rate is 5.0X10 ⁹ ～1.0×10 ¹³ n/cm ² ·s。

Furthermore, the gas cooled reactor and the gas cooled fast reactor adopt uranium fuel or uranium thorium MOX fuel, wherein the enrichment degree of U-235 is not lower than 4.5%; if uranium plutonium MOX fuel, thorium plutonium MOX fuel or uranium thorium plutonium MOX fuel is used, the enrichment degree of Pu-239 is not less than 5%.

By applying the technical scheme of the invention, at least the following beneficial effects are realized:

1. the tritium producing module system is arranged on the periphery of the reactor core in the gas cooled reactor to produce tritium elements, so that the irradiation hazard of neutron leakage of the high reactor core of the gas cooled reactor to reactor components, external personnel and equipment can be solved, and the thicknesses of the reflection layer, the moderation layer and the external shielding body of the gas cooled reactor can be reduced.

2. The first gas accelerating device is arranged at the coolant inlet of the reactor in the gas cooled reactor, so that the flow rate of a gas medium in the gas cooled reactor can be improved, the circulation speed and efficiency of the gas medium are enhanced, and the gas medium physical parameter adjusting system is arranged, so that parameters such as the pressure and the flow rate of the gas medium at the air inlet section of the first gas accelerating device can be adjusted and changed according to different operating conditions of the reactor, such as different operating powers, and the automatic adjustment of the cooling efficiency of the reactor and the tritium carrier band efficiency is realized.

3. The gas cooled reactor can improve the flow rate of tritium medium in the tritium producing module system by arranging the second gas accelerating device at the coolant inlet of the tritium producing module system, so that the flow rate, pressure and density of the gas medium entering different structural layers of the tritium producing module system are different, the capability and efficiency of carrying tritium by the gas medium are enhanced, and simultaneously, the generated ultrasonic fluctuation can remove the tritium deposited and adhered on the pipe wall of the flow channel and in the tritium producing module system, so that the sedimentation and adsorption loss of the tritium are reduced.

4. The gas cooled reactor is provided with a splitter plate to split the gas coolant entering the reactor core and the gas medium entering the tritium production module system, so that the high tritium gas medium after entering the tritium production module system is not mixed with the reactor core coolant, and the tritium radioactivity level of the gas medium in the reactor core coolant system is maintained; and the parameters of the gas medium entering different systems are respectively regulated, so that the reactor coolant entering the tritium-producing module system is coupled with the second gas accelerating device, and the tritium carrying capacity of the gas medium in the tritium-producing module system is enhanced.

5. The tritium producing module system of the gas cooled reactor can better realize neutron multiplication and tritium element generation functions by designing the structures of the neutron multiplication layer and the tritium multiplication layer or the tritium multiplication layer, and the positions and the structures of the tritium pipelines are designed in the tritium producing module system, so that the transfer capacity and the efficiency of tritium in the tritium producing module system can be enhanced.

6. The fuel assembly is designed to be axially divided into a plurality of sections in the high-flux gas cooled reactor or the high-flux gas cooled fast reactor, fuels with different enrichment degrees and easy fissile nuclides are adopted, the flow velocity of runner gas in the reactor core and the fuel assembly is increased through temperature difference and pressure difference, the cooling efficiency of the reactor core is improved, the axial power distribution of the fuel assembly is flattened, and the safety of the reactor core is improved.

7. The shape of the coolant flow channel of the fuel assembly is designed in the high-flux gas cooled reactor or the high-flux gas cooled fast reactor, and the third gas accelerating device is designed in the coolant flow channel of the fuel assembly, so that the flow rate of the coolant gas is further increased, the cooling efficiency of the fuel is enhanced, and the tritium production capacity under the conditions of high neutron fluence and high temperature is realized.

In order to achieve the above object, according to another aspect of the present invention, there is provided a combined system of a gas-cooled reactor and a fusion reactor, which comprises the fusion reactor and further comprises the gas-cooled reactor, wherein the fusion reactor comprises various fusion reactors using tritium and/or helium-3 as fusion fuel and fusion-fission hybrid reactors; the combined system also comprises a tritium supply system, wherein the tritium supply system is connected with the gas-cooled reactor and also connected with the fusion reactor, the gas-cooled reactor produces tritium, and tritium fuel and/or helium-3 fuel is supplied to the fusion reactor through the tritium supply system.

Further, the tritium providing system comprises a tritium collecting system, a tritium treatment and storage system and a tritium fuel supplementing system which are connected in sequence, wherein the tritium collecting system is communicated with the gas cooled reactor, and the tritium fuel supplementing system is communicated with the fusion reactor.

Further, the tritium treatment 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 a tritium extraction system, a tritium purification and separation system and a tritium storage system, and monitors equipment and facilities in each system.

Further, 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 comprises: a feed pretreatment system and a tritium injection system.

Further, the input of the tritium collection system is communicated with a tritium-producing module system of the gas cooled reactor, and reactor coolant and tritium-containing medium in the tritium-producing module system enter a tritium supply system.

Further, the input of the tritium collecting system is communicated with the reactor core of the gas-cooled reactor, reactor coolant in the reactor core enters the tritium providing system, and the reactor coolant after separation, purification and tritium removal is returned to the gas-cooled reactor for reuse.

Further, the combined system also comprises a fission fuel bi-directional supply system, comprising a first nuclear fuel supply system and a second nuclear fuel supply system, wherein the gas cooled reactor supplies 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 fuels.

Further, the fusion stack provides Pu-239 and/or U-233 to the gas cooled stack via a second nuclear fuel supply system.

1. the combined system can provide tritium fuel and/or helium-3 fuel for the fusion reactor or the fusion fission hybrid reactor by arranging the tritium providing system and collecting, processing, storing, transporting and the like the tritium generated by the gas cooling reactor in the tritium providing system so as to solve the problems of tritium self-maintenance and fuel supplementation of the fusion reactor and the fusion fission hybrid reactor.

2. The combined system is provided with the fission fuel bidirectional supply system, so that the gas-cooled reactor and the fusion reactor in the combined system can mutually provide nuclear fuel, the aim of combined symbiosis of the gas-cooled reactor and the fusion reactor is fulfilled, the utilization rate of the fission fuel is increased, the total radioactive waste is reduced, and the economical efficiency of the combined system is enhanced.

3. The integrated system is communicated with the tritium production module system of the gas cooled reactor and the reactor core through the input of the tritium collection system, when tritium extraction or tritium purification is not needed for the reactor core coolant, the communication between the tritium production module system and the tritium collection system can be only started, and the reactor coolant after tritium removal through separation and purification can be returned to the gas cooled reactor for reuse, so that the economical efficiency is improved.

Drawings

The accompanying drawings, which are included to provide a further understanding of the invention and are incorporated in and constitute a part of this specification, illustrate embodiments of the invention and together with the description serve to explain the invention. In the drawings:

FIG. 1 shows a schematic longitudinal cross-sectional view of the gas cooled reactor main structure of example 1;

FIG. 2 shows a schematic cross-sectional view of the gas cooled reactor of example 1;

FIG. 3 is a schematic diagram showing a cross-sectional specific structure of the air-cooled reactor of embodiment 1;

FIG. 4 shows a schematic longitudinal cross-section of a tritium-producing module system of the gas cooled stack of example 1;

FIG. 5 is a schematic diagram showing a cross-sectional specific structure of the air-cooled reactor of embodiment 2;

FIG. 6 is a schematic diagram showing a cross-sectional specific structure of the air-cooled reactor of embodiment 3;

FIG. 7 shows a schematic diagram of the combined system of the gas cooled reactor and the fusion reactor of example 4.

Wherein the above figures include the following reference numerals:

1. a core; 11. a fuel assembly; 12. a third gas acceleration device; 13. a fuel element; 2. a neutron modifying layer; 3. a nuclear fuel seal and isolation layer;

4. a tritium producing module system; 41. a second gas accelerating device; 42. a cladding; 43. a first neutron multiplication layer; 44. a tritium proliferation layer; 45. a tritium multiplication layer; 451. a neutron multiplication unit; 452. a tritium proliferation section; 46. a tritium pipe; 47. a partition plate; 48. a first moderating layer; 49. irradiating a production layer of the product;

5. A reactor pressure vessel; 6. a first gas acceleration device; 61. a gaseous medium physical parameter adjusting system; 62. a connecting pipe; 7. a diverter plate;

8. a tritium supply system; 81. a tritium collection system; 82. tritium treatment and storage systems; 821. a tritium extraction system; 822. tritium purification and separation systems; 823. a tritium storage system; 83. a tritium fuel replenishment system;

9. a fissionable fuel bi-directional supply system; 91. a first nuclear fuel supply system; 92. a second nuclear fuel supply system;

100. a gas cooled reactor; 200. fusion stacks.

Detailed Description

It should be noted that, without conflict, the embodiments of the present invention and features of the embodiments may be combined with each other. The invention will be described in detail below with reference to the drawings in connection with embodiments.

The invention is described in further detail below in connection with specific examples which are not to be construed as limiting the scope of the invention as claimed. The term "comprising" when used indicates the presence of a feature, but does not preclude the presence or addition of one or more other features; the positional or positional relationship indicated by the terms "transverse", "upper", "lower", "front", "rear", "left", "right", "top", "bottom", "inner", "outer", etc., are based on the positional or positional relationship shown in the drawings, are for convenience of description only, and are not indicative or implying that the apparatus or element in question must have a particular orientation, be constructed and operated in a particular orientation, and therefore should not be construed as limiting the invention; furthermore, the terms "first," "second," and the like, are used for descriptive purposes only and are not to be construed as indicating or implying relative importance.

In the description, unless clearly indicated and limited otherwise, the terms "mounted," "connected," and "connected" are to be construed broadly, and may be, for example, fixedly connected, detachably connected, or integrally connected; can be directly connected or indirectly connected through an intermediate medium, and can be communication between two elements. The specific meaning of the above terms in the present application will be understood in specific cases by those of ordinary skill in the art. Furthermore, in the description of the present application, unless otherwise indicated, the meaning of "a plurality" is two or more.

The tritium producing module system is arranged in the gas cooled reactor, so that the gas cooled reactor has the function of producing tritium elements.

Compared with other pile types, the gas cooled pile tritium production has three physical characteristic advantages. First, the gas cooled reactor has the physical characteristic of high core neutron leakage rate, by arranging a tritium producing module system at the periphery of the gas cooled reactor core, tritium element is produced by utilizing the action of neutrons leaked from the reactor core and tritium proliferation materials in the tritium producing module system, meanwhile, the neutron irradiation damage and the radiation level outside the reactor of key equipment such as a pressure vessel are reduced by utilizing the high neutron reaction section of the materials, the original graphite reflecting layer without additional value is replaced by the tritium producing module system with value, and the thicknesses of the gas cooled reactor reflecting layer, the slowing-down layer and the external shielding body can be reduced. Secondly, the temperature in the gas cooled reactor is high, generally over 400-800 ℃, which is favorable for the release and diffusion of tritium in a tritium-producing module system and has excellent tritium on-line extraction conditions. Third, the gas cooling reactor gas coolant has good tritium carrying capacity, and the gas coolant has stable physical and chemical properties (such as He) and large difference with tritium physical and chemical properties (such as carbon dioxide), and is easy for tritium separation and purification.

Example 1:

the invention provides a gas cooled reactor, which comprises a reactor core 1, a nuclear fuel seal isolation layer 3 and a reactor pressure vessel 5 which are arranged from inside to outside along the radial direction of the gas cooled reactor, and also comprises a tritium producing module system 4, wherein the tritium producing module system 4 is positioned at the periphery of the reactor core 1 and between the nuclear fuel seal isolation layer 3 and the reactor pressure vessel 5, and the tritium producing module system 4 comprises tritium proliferation materials which react with neutrons generated by the reactor core 1 to generate tritium elements. Wherein the nuclear fuel seal and isolation layer 3 comprises a metal container or coaming plate and also comprises a fixed supporting member.

The tritium producing module system 4 is arranged on the periphery of the reactor core in the gas cooling reactor to produce tritium elements, so that the irradiation hazard of neutron leakage of the high reactor core of the gas cooling reactor to reactor components, external personnel and equipment can be solved, and the thicknesses of the reflection layer, the moderation layer and the external shielding body of the gas cooling reactor can be reduced.

As shown in fig. 1, the gas cooled reactor includes a reactor coolant inlet where a first gas accelerator 6 is provided, and a gas medium physical parameter adjustment system 61 is provided on the first gas accelerator 6.

The first gas accelerator 6 has a structure with a variable cross-sectional area, and is not limited to a tubular structure with a variable cross-sectional area, a plate-like structure, or the like. The device comprises a contraction section, a narrow throat section and an expansion section which are sequentially connected along the gas flowing direction, wherein the sectional area of the contraction section is changed from large to small along the flowing direction, and the sectional area of the expansion section is changed from small to large along the flowing direction. Preferably, the first gas accelerator 6 has a laval nozzle or similar structure designed using bernoulli's principle and related physics principles. Furthermore, in other embodiments, the first gas accelerating device 6 may include only a constriction section therein, and may also function to accelerate the gas.

Specifically, the gas medium physical parameter adjusting system 61 includes a plurality of connecting pipes 62 and a valve assembly, a plurality of holes are formed on the wall surface of the gas inlet section of the first gas accelerating device 6, the holes are respectively communicated with the plurality of connecting pipes 62, the valve assembly is arranged on the plurality of connecting pipes 62, the valve assembly includes one or more of a regulating valve, a constant pressure check valve and a variable pressure check valve, and different valves may be arranged on different connecting pipes 62.

The first gas accelerating device is arranged at the coolant inlet of the reactor in the gas-cooled reactor, so that the flow rate of a gas medium in the gas-cooled reactor can be improved, and the circulation speed and efficiency of the gas medium are improved; by setting the physical parameter adjusting system of the gas medium, parameters such as pressure intensity, flow velocity and the like of the gas medium at the gas inlet section of the first gas accelerating device can be adjusted and changed according to different operation conditions of the reactor, such as different operation powers, so that the automatic adjustment of the cooling efficiency and the tritium carrying efficiency of the reactor is realized.

As shown in fig. 1, the reactor coolant inlet is respectively communicated with the reactor core 1 and the tritium production module system 4, the gas cooled reactor 100 comprises a splitter plate 7, the splitter plate 7 is positioned between the first gas accelerator 6 and the reactor core 1 and also positioned between the first gas accelerator 6 and the tritium production module system 4, and the gas cooled reactor is provided with the splitter plate to isolate the gas coolant entering the reactor core from the gas medium entering the tritium production module system, so that the high tritium gas medium is not mixed into the reactor core coolant after entering the tritium production module system, and the tritium radioactivity level of the gas medium in the reactor core coolant system is maintained.

Furthermore, in this embodiment, the gas parameters of the reactor coolant entering the core 1 and the tritium production module system 4, respectively, can be adjusted by the diverter plate 7.

As shown in FIG. 4, the tritium production module system 4 comprises a tritium production module system coolant inlet, and a part of reactor coolant is split by a splitter plate and flows into the tritium production module system 4 through the tritium production module system coolant inlet. A second gas accelerator 41 is provided at the tritium producing module system coolant inlet.

The second gas accelerator 41 has a structure with a variable cross-sectional area, and is not limited to a tubular structure with a variable cross-sectional area, a plate-like structure, or the like. The device comprises a contraction section, a narrow throat section and an expansion section which are sequentially connected along the gas flowing direction, wherein the sectional area of the contraction section is changed from large to small along the flowing direction, and the sectional area of the expansion section is changed from small to large along the flowing direction. Preferably, the second gas accelerator 41 has a laval nozzle or similar structure designed using bernoulli's principle and related physics principles. Furthermore, in other embodiments, the second gas accelerating device 41 may include only a constriction section therein, and may also function to accelerate the gas.

As shown in fig. 1, the splitter plate 7 is preferably connected with the first gas accelerator 6, and the flow rate of the gas flow can be controlled by adjusting the size of the opening at the joint of the splitter plate 7 and the first gas accelerator 6. And then, according to the parameter range of the gas medium after passing through the first gas accelerating device 6, the air inflow and the parameters of the coolant respectively entering the reactor core and the tritium production module system are further adjusted by adjusting the parameters such as the space volume between the splitter plate 7 and the reactor pressure vessel 5. The adjustment of the gas parameters is performed sequentially through the first gas accelerating device 6 and the splitter plate 7, so that the reactor coolant entering the tritium producing module system 4 can be coupled with the second gas accelerating device 41, and the tritium carrying capacity of the gas medium in the tritium producing module system is enhanced.

The following describes the specific structure of the tritium producing module system 4 in this embodiment in detail:

as shown in FIG. 3, tritium producing module system 4 includes cladding 42 and tritium producing layer groups, cladding 42 being disposed radially spaced apart from gas cooled reactor 100, cladding 42 being located at the radially outermost layer of the tritium producing module system along the reactor, and tritium producing layer groups being located between cladding 42. The tritium-producing layer group at least comprises one of a tritium proliferation layer 44 and a tritium proliferation multiplication layer 45, wherein the tritium proliferation layer 44 and the tritium proliferation multiplication layer 45 both comprise a tritium-producing region, and the tritium-producing region comprises a tritium proliferation material.

A first neutron multiplication layer 43 may also be disposed in the tritium producing layer group, the first neutron multiplication layer 43 comprising neutron multiplication material. The first neutron multiplication layer 43 may be co-configured with either or both of the tritium multiplication layer 44 and the tritium multiplication layer 45. Preferably, the first neutron multiplication layer 43 is provided simultaneously with the tritium multiplication layer 44 alone in the tritium producing layer group.

As shown in connection with fig. 3 and 4, the tritium producing group further includes a tritium conduit 46 for communication of reactor coolant and tritium containing medium, the tritium conduit 46 extending in an axial direction of the gas cooled reactor 100, the walls of the tritium conduit 46 being provided with a plurality of holes such that the interior of the tritium conduit 46 is in fluid communication with the tritium producing region.

Tritium conduit 46 is a single or multi-layer conduit. Preferably, tritium conduit 46 is a multi-layer conduit, shown in FIG. 4 as a two-layer conduit, with a plurality of holes being formed in any one or more of the walls of the multi-layer conduit. It is further preferred that the positions of the holes in the walls of any adjacent two layers of piping on the tritium piping are offset from each other along the direction of extension of the tritium piping 46. The tritium production module system is provided with a plurality of layers of tritium pipelines, holes are formed in the pipe walls, and positions of the holes are arranged, so that tritium elements are easier to release and diffuse from the tritium production module system into the tritium pipelines.

Further, the tritium conduit 46 is in communication with the second gas accelerating device 41 such that the flow rate of the gaseous medium into the tritium conduit is greatly increased. The flow rate of the tritium-containing medium in the tritium-producing module system 4 can be improved, so that the flow rates, pressures and densities of the gas mediums entering different structural layers of the tritium-producing module system 4 are different, and the tritium carrying capacity and efficiency of the gas mediums are enhanced. Simultaneously, the generated ultrasonic wave can remove the tritium deposited and attached on the pipe wall of the flow channel and in the tritium producing module system 4, thereby reducing the sedimentation and adsorption loss of the tritium. In addition, the second gas acceleration device 41 cooperates with the holes in the tube wall to increase the flow rate of the tritium tube 46 from the outside to the inner layer and decrease the pressure layer by layer, thereby further enhancing the efficiency of the release and diffusion of tritium into the tritium tube.

As shown in connection with fig. 3 and 4, in this embodiment, the tritium producing group includes a first neutron multiplication layer 43 and a tritium multiplication layer 44 disposed radially of the gas cooled reactor, the tritium multiplication layer 44 being located outside of the first neutron multiplication layer 43, and at least a portion of the tritium conduit 46 being located within the tritium multiplication layer 44.

The tritium producing module system 4 further comprises a partition plate 47, wherein the partition plate 47 is arranged between different types of layers in the tritium producing layer group, and the partition plate 47 can be arranged between the tritium producing layer group and other layers.

In other embodiments, the tritium producing group of layers includes a first circulation structure in which the first neutron multiplication layer 43 and the tritium multiplication layer 44 disposed radially of the reactor circulate a plurality of times, and a spacer 47 may be disposed between different layers of the tritium producing group of layers. The circulating structure can enhance the utilization rate of neutrons by the tritium production module system.

The tritium producing modular system 4 further includes a tritium permeation preventing layer adjacent to the cladding 42, the tritium permeation preventing layer comprising an oxide and a titanium-containing ceramic, the oxide comprising one or more of the following: cr (Cr) ₂ O ₃ 、Al ₂ O ₃ 、Ti ₂ O ₂ The titanium-containing ceramic is preferably a titanium aluminum carbide ceramic. The tritium-proof permeation layer can effectively prevent tritium elements in the tritium-producing module system from permeating to the outside of the tritium-producing module system to cause loss.

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

Tritium producing module system 4 also includes a radiation product producing layer 49, the material of radiation product producing layer 49 comprising one or more of the following: np-237 and its compounds for producing Pu-238, co-59 and its compounds for producing Co-60; spacers 47 are provided on either side of the irradiation product production layer 49, and the irradiation product production layer 49 is located outside of the tritium proliferation layer 44. For other embodiments where there is a radiation product production requirement, the radiation product producing layer 49 can also be located elsewhere in the tritium breeder layer 44, including inboard or circumferentially laterally in the radial direction of the gas cooled stack.

The tritium producing module system 4 further includes a first reflective or first moderating layer 48, the first reflective or first moderating layer 48 being located outside of the irradiation product production layer 49, the material of the first reflective or first moderating layer 48 comprising one or more of the following: graphite, isostatic graphite, nuclear grade graphite, boron carbide, silicon carbide, boron-containing silicon carbide, beryllium oxide, or beryllium-containing compounds. The reflection layer is arranged at the position and can reflect neutrons, so that the neutron utilization rate is improved, and the tritium yield is increased.

In other embodiments, the radiation product producing layer 49 may be disposed between any two of the first neutron multiplication layer, tritium multiplication layer, first moderation layer, or first reflection layer, with spacers disposed between the radiation product producing layer and the other layers.

To sum up, in the present embodiment, preferably, the tritium producing module system includes an envelope 42, a tritium preventing permeation layer, a first neutron multiplication layer 43, a partition 47, a tritium multiplication layer 44, a partition 47, a irradiated product production layer 49, a partition 47, a first reflection layer or a first slowing layer 48, a tritium preventing permeation layer, and an envelope 42, which are sequentially arranged from inside to outside in the radial direction of the reactor.

Specifically, the first neutron multiplication layer 43 and the tritium multiplication layer 44 each have a structure in which a material ball is filled in a ball bed. Wherein the first neutron multiplication layer comprises a neutron multiplication material sphere having neutron multiplication material therein, the neutron multiplication material comprising beryllium and a beryllium-containing compound, such as beryllium, beO, or beryllium-containing ceramic.

The tritium proliferation layer 44 comprises a tritium proliferation material ball, the tritium proliferation material ball is provided with a tritium proliferation material, and the tritium proliferation material comprises one or a mixture of several of the following substances: li (Li) ₂ O、Li ₂ TiO ₃ 、LiAlO ₂ 、Li ₄ SiO ₄ 、Li ₂ ZrO ₃ And (3) ceramics.

The diameters of the neutron multiplication material balls and the tritium multiplication material balls are 0.1mm-10mm, and the filling rate is 40% -80%. Preferably, the diameter is 0.2mm-2mm, the filling rate is 50% -70%, and the effects of neutron multiplication and tritium proliferation are better.

Preferably, the tritium breeder material has an enrichment of Li-6 of 7.5% to 90%, an enrichment of Li-7 of 10% to 92.5%, and a total of Li-6 and Li-7 of 100%. Tritium breeder material with an enrichment of 50% -92.5% of Li-7 is arranged at a position close to the reactor core, and tritium breeder material with an enrichment of 50% -90% of Li-6 is arranged at a position far away from the reactor core.

The fast neutrons with higher energy of more than 1.0MeV in the hard neutron energy spectrum near the reactor core position are utilized to react with Li-7 to produce tritium (the fast neutrons with the energy of 2.47MeV have large action cross sections), and the neutron energy spectrum is softened through the moderation of the front material layer to improve the proportion of low energy and thermal neutrons, so that the tritium production rate of the fast neutrons and Li-6 is increased, the manufacturing cost of the proliferation material is finally reduced, and the tritium production rate is improved.

The tritium producing module system also includes coolant channels, similar in function to tritium conduits, for circulation of reactor coolant and/or tritium containing medium, the coolant channels being disposed in the interstices between the layers, and/or within the cladding and/or separator plates, in the tritium producing module system.

Preferably, the thickness of the envelope and/or separator is greater than 1mm, and if coolant pipes are provided in the envelope and/or separator, the thickness of the envelope and/or separator with coolant passages is greater than 3mm.

The tritium producing module system can be completely or partially surrounded on the periphery of the reactor core in the circumferential direction, the periphery of the reactor core can comprise a plurality of tritium producing module systems with the same or different structures, and the tritium producing module systems can be uniformly or unevenly arranged in an angle range of 360 degrees or uniformly or unevenly arranged in a partial angle range of the periphery of the reactor core at intervals of a certain angle.

The tritium producing modular system shape includes a combination of one or more of the following shapes: 360-degree integral hollow circular column, hollow arc column in 1-359 degree angle, column, polygon prism, trapezoid cross section column, sector cross section column, cube.

The thickness of the tritium producing module system along the radial direction of the reactor is 1cm-100cm. Engineering is preferred, and the thickness of the tritium-producing module system is 15cm-60cm.

Preferably, as shown in FIG. 3, the tritium producing module system is in the shape of a circular cylinder that completely surrounds the periphery of the reactor core in the circumferential direction. The tritium producing module system is formed by seamlessly splicing a plurality of tritium producing submodules in the circumferential direction, and the number of the tritium producing submodules is in the range of 4-24. Namely, the shape of the tritium-producing submodule is a sector cross section column shape with an angle of 15-90 degrees.

It is further preferred that spacers be provided between adjacent tritium producing submodules, as shown in fig. 3, to prevent direct contact of adjacent tritium producing submodule materials. The tritium pipeline circumferentially surrounds the reactor core in the tritium proliferation layer, and 2-6 tritium pipelines are arranged in each tritium production submodule.

The tritium production module system is completely surrounded on the periphery of the reactor in the circumferential direction and is formed by splicing a certain number of tritium production sub-modules, so that the maximum tritium production effect is realized for the reactor, and when a part of tritium production sub-modules have problems, the tritium production sub-modules are conveniently replaced, so that the tritium production stability of the reactor is ensured.

As shown in fig. 1, the core 1 includes a fuel assembly 11, and the fuel assembly 11 is divided into a plurality of segments in an axial direction of the gas cooled reactor, and the fissionable nuclide enrichment of the fuel assembly 11 increases segment by segment from an inlet end to an outlet end of the fuel assembly 11. The flow channel gas flow velocity in the reactor core and the fuel assembly is increased through the temperature difference and the pressure difference, the reactor core cooling efficiency is improved, the fuel assembly axial power distribution is flattened, and the reactor core safety is improved.

Preferably, the fuel assembly 11 is divided into 3-8 segments in the axial direction of the gas cooled reactor 100, and the multi-segment fuel assembly 11 uses fuels of 3-4 different fissionable nuclides.

Preferably, the fuel assembly 11 includes a fuel assembly coolant flow passage, on which the third gas accelerating device 12 is disposed, and the third gas accelerating device 12 adopts a structure similar to the first gas accelerating device 6 and the second gas accelerating device 41, adopts a cross-sectional area changing structure, and includes a constriction section, a narrow throat section, and an expansion section, which are sequentially connected in the gas flowing direction. Preferably, a Laval nozzle structure may be employed. A third gas accelerating device is designed in the coolant flow passage of the fuel assembly to further increase the flow rate of the coolant gas and enhance the cooling efficiency of the fuel.

It should be noted that the above fuel assembly segmentation and arrangement of the third gas accelerator 12 is more applicable to high flux gas cooled stacks or fast high flux gas cooled stacks, and may not be employed for other types of gas cooled stacks.

A coolant flow passage and/or a second neutron multiplication layer and/or a second reflection layer and/or a second moderation layer can be arranged between the nuclear fuel seal isolation layer 3 and the tritium production module system 4; a coolant flow path and/or a third neutron multiplication layer and/or a third reflection layer and/or a third moderation layer may be provided between the reactor pressure vessel 5 and the tritium production module system 4.

The nuclear fuel seal and spacer layer 3 comprises a metal container or shroud and also comprises a fixed support member. As shown in fig. 2, a neutron modifying layer 2 is disposed between the core 1 and the nuclear fuel containment layer 3, and the neutron modifying layer 2 includes a coolant flow path, and/or a fourth neutron multiplying layer and/or a fourth reflecting layer and/or a fourth moderating layer.

For a typical gas cooled reactor, a fourth neutron multiplication layer is provided in the neutron modifying layer 2. For a cold fast reactor, the neutron modifying layer 2 of the gas cooled reactor may be provided as a fourth moderating layer.

The thermal neutron fluence rate of the tritium-producing module system 4 of the gas cooled reactor is 1.0 multiplied by 10 ¹⁰ ～2.0×10 ¹³ n/cm ² S, the fast neutron fluence rate is 5.0X10 ⁹ ～5.0×10 ¹² n/cm ² S; if the gas cooled reactor 100 is a gas cooled fast reactor, the thermal neutron fluence rate of the tritium production module system 4 is 1.0X10 ¹⁰ ～2.0×10 ¹³ n/cm ² S, the fast neutron fluence rate is 5.0X10 ⁹ ～1.0×10 ¹³ n/cm ² ·s。

The reactor coolant is a gas, the cooling gas comprising: inert gases such as helium (He), or carbon dioxide (CO) ₂ ) And the like, and is stable in physical and chemical properties. Preferably, the engineered reactor coolant gas is an inert gas such as helium (He).

The fuel element shape includes: spherical, columnar, plate-like, block-like, cross-shaped, arc-shaped plate-like, and hollow columnar. The columnar fuel element cross-sectional shape includes: round, regular polygon (e.g., square, regular hexagon, regular octagon, etc.). The inner and outer shape of the cross section of the hollow cylindrical fuel element comprises: round, regular polygon (such as square, regular hexagon, regular octagon, etc.), the inner side and the outer side are the same shape or different shapes.

Reactor core fuelA uranium-, thorium-, plutonium-containing substance comprising: AO (AO) ₂ AN AC, AN, or MOX ceramic fuel, or a TRISO type fuel coated with particles. A is one of uranium, thorium and plutonium, and MOX comprises any two or three of uranium, thorium and plutonium.

The gas cooled reactor and the gas cooled fast reactor adopt uranium fuel or uranium thorium MOX fuel, wherein the enrichment degree of U-235 is not lower than 4.5%; if uranium plutonium MOX fuel, thorium plutonium MOX fuel or uranium thorium plutonium MOX fuel is used, the enrichment degree of Pu-239 is not less than 5%.

Example 2:

the gas cooled reactor structure in this embodiment is substantially the same as that in embodiment 1 except that: the tritium producing modular system 4 is structurally different. As shown in FIG. 5, the tritium producing module system of example 2 consists of cladding 42 and tritium multiplication layer 45 between the cladding. A tritium-proof layer may also be provided adjacent to the envelope 42.

Specifically, the tritium producing layer group in the present embodiment includes a tritium multiplication layer 45, the tritium multiplication layer 45 includes a neutron multiplication portion 451 and a cylindrical tritium multiplication portion 452, and the plurality of tritium multiplication portions 452 are uniformly arranged in the neutron multiplication portion 451, so that the neutron fluence in each tritium multiplication portion 452 is at the same order of magnitude level. Preferably, a spacer 47 is provided around the circumference of the tritium multiplication section 452 in a cylindrical shape to separate the materials of the neutron multiplication section 451 and the tritium multiplication section 452. The volume ratio of neutron multiplication section 451 to tritium multiplication section 452 is in the range of 2:1 to 8:1, with tritium conduits 46 being arranged in an array within tritium multiplication section 452.

Preferably, the number of tritium breeder portions 452 in each tritium producing submodule is no more than 6, as shown in fig. 5 as 3. So that the distance difference between the material at all locations within the tritium breeding section 452 and the nearest tritium conduit 46 is 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.

In other embodiments, the tritium producing group of layers includes a second circulation structure in which the first neutron multiplication layer 43, the tritium multiplication layer 44, and the tritium multiplication layer 45 disposed radially of the reactor circulate a plurality of times. A spacer 47 may be provided between the different layers. Wherein the first neutron multiplication layer 43, tritium multiplication layer 44 are of the shape and structure as described in example 1. The circulation structure has higher utilization rate of neutrons in the reactor.

In other embodiments, tritium producing layer groups may be provided as a combination of tritium multiplication layer 45 and first neutron multiplication layer 43.

Specifically, the tritium multiplication layer 45 may be provided as a mixture of neutron multiplication material pellets and tritium multiplication material pellets. The tritium multiplication layer 45 may also include a tritium multiplication material pellet, the center portion of the tritium multiplication material pellet having tritium multiplication material, and the shell portion of the tritium multiplication material pellet having neutron multiplication material.

If the tritium multiplication layer 45 is a mixture of neutron multiplication material balls and tritium multiplication material balls, the proportion of the neutron multiplication material balls to the tritium multiplication material balls is 2:1 to 8: 1. The diameters of the neutron multiplication material balls, the tritium multiplication material balls or the tritium multiplication material balls are 0.1mm-10mm, and the filling rate is 40% -80%. Preferably, the diameter is selected to be 0.2mm-2mm, and the filling rate is 50% -70%. The neutron multiplication and tritium multiplication effects are good.

Note that the structure of the tritium multiplication layer 45 described in this example is merely preferable, and the structure of the tritium multiplication layer 45 is not limited to the form described in fig. 5. For example, the cross-sectional shape of the tritium multiplication section 452 may be other shapes, or the tritium multiplication layer 45 may include only a pellet of tritium multiplication material.

In this embodiment, the irradiation product production layer 49 is preferably not provided. Meanwhile, the neutron multiplier 451 may be used as a neutron reflecting layer, and the first reflecting layer or the first slowing layer 48 may not be provided in the tritium producing module system. Thereby greatly simplifying the structure of the tritium-producing module system.

In addition, to allow for isotope production, no more than one-half of the total amount of tritium breeder 452 material may be filled with isotope production material.

In other embodiments, either the irradiation product production layer 49 or the first reflective layer or the first moderating layer 48 may also be provided in the tritium producing module system described in this embodiment.

In summary, from the above description, it can be seen that the following technical effects are at least achieved in embodiment 1 and embodiment 2:

Example 3:

the gas cooled reactor structure in this example is substantially the same as that of examples 1 and 2, and as shown in FIG. 6, a gas cooled reactor substantially the same as tritium producing module system 4 of example 1 is used herein 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.

In particular, to further increase neutron fluence at tritium production module systems, it is preferred that the core 1 herein employ a compact array of discharged arcuate columnar fuel elements. For high flux gas cooled stacks, coolant channels may be provided in neutron modifying layer 2. For high flux gas cooled fast stacks, coolant channels may be provided in neutron modifying layer 2 and a fourth moderating layer or a fourth reflecting layer may be provided.

Further, for high flux gas cooled stacks and high flux gas cooled fast stacks, the core uses uranium fuel with enrichment of U-235 not less than 15%, or MOX fuel with enrichment of U-235 0.3% and enrichment of Pu-239 not less than 10%.

Referring to fig. 1, as shown in fig. 1, the core 1 includes a fuel assembly 11, and the fuel assembly 11 is divided into a plurality of segments in an axial direction of the gas cooled reactor, and the enrichment degree of the fissionable nuclide of the fuel assembly 11 increases segment by segment from an inlet end to an outlet end of the fuel assembly 11.

The fuel assembly is designed to be axially divided into a plurality of sections in the high-flux gas cooled reactor or the high-flux gas cooled fast reactor, fuels with different enrichment degrees and easy fissile nuclides are adopted, the flow velocity of runner gas in the reactor core and the fuel assembly is increased through temperature difference and pressure difference, the cooling efficiency of the reactor core is improved, the axial power distribution of the fuel assembly is flattened, and the safety of the reactor core is improved.

Preferably, the fuel assembly 11 includes a fuel assembly coolant flow passage on which the third gas accelerator 12 is disposed, and the third gas accelerator 12 is configured similarly to the first gas accelerator 6 and the second gas accelerator 41, preferably in a laval nozzle configuration. A third gas accelerating device is designed in the coolant flow passage of the fuel assembly to further increase the flow rate of the coolant gas and enhance the cooling efficiency of the fuel.

As shown in fig. 6, the fuel assembly 11 is generally cylindrical and includes a plurality of fuel elements 13. The fuel assembly coolant flow channels are divided into multiple layers along the radial direction of the air cooled reactor, wherein the fuel assembly coolant flow channels comprise interlayer flow channels, and the interlayer flow channels are gaps of 2-20 mm between the fuel assemblies 11 of different layers.

Furthermore, the fuel assembly 11 is further divided into a plurality of sectors in the circumferential direction of the gas cooled reactor 100, and the angle of each sector may be different, so that each layer of fuel assembly 11 has a plurality of fuel elements 13. The fuel assembly coolant flow passage also includes axial channels, each fuel element 13 having a plurality of axial channels along the axial direction of the gas cooled stack 100.

Specifically, as shown in fig. 6, the number of axial passages on each fuel element 13 is determined according to the following formula: Where n is the number of axial channels, θ is the angle of 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 in the radial direction of the gas cooled reactor from inside to outside. This design allows each fuel element to have a suitable number of axial passages, which is advantageous for improving the cooling efficiency of the overall fuel assembly 11.

The shape of the coolant flow channel of the fuel assembly is designed in the high-flux gas-cooled reactor or the high-flux gas-cooled fast reactor, and the third gas accelerating device is designed in the coolant flow channel of the fuel assembly, so that the flow rate of the coolant gas is further increased, the cooling efficiency of the fuel is enhanced, and the tritium production capability under the conditions of high neutron fluence and high temperature in the high-flux gas-cooled reactor or the high-flux gas-cooled fast reactor is realized.

Thermal neutrons of tritium-producing modular system 4 of high-flux gas cooled reactorThe fluence rate was 1.0X10 ¹¹ ～5.0×10 ¹⁵ n/cm ² S, the fast neutron fluence rate is 1.5X10 ¹⁰ ～1.0×10 ¹⁵ n/cm ² S; the thermal neutron fluence rate of the tritium-producing module system 4 of the high-flux gas cooled fast reactor is 1.0 multiplied by 10 ¹¹ ～5.0×10 ¹⁵ n/cm ² S, the fast neutron fluence rate is 3X 10 ¹² ～5.0×10 ¹⁵ n/cm ² ·s。

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

1. the fuel assembly is designed to be axially divided into a plurality of sections in the high-flux gas cooled reactor or the high-flux gas cooled fast reactor, fuels with different enrichment degrees and easy fissile nuclides are adopted, the flow velocity of runner gas in the reactor core and the fuel assembly is increased through temperature difference and pressure difference, the cooling efficiency of the reactor core is improved, the axial power distribution of the fuel assembly is flattened, and the safety of the reactor core is improved.

2. The shape of the coolant flow channel of the fuel assembly is designed in the high-flux gas cooled reactor or the high-flux gas cooled fast reactor, and the third gas accelerating device is designed in the coolant flow channel of the fuel assembly, so that the flow rate of the coolant gas is further increased, the cooling efficiency of the fuel is enhanced, and the tritium production capacity under the conditions of high neutron fluence and high temperature is realized.

3. The high-efficiency cooling capacity of the reactor core is guaranteed by arranging the first gas accelerating device in the gas cooled reactor, arranging the coolant flow channels in the reactor core and the fuel assembly, arranging the third gas accelerating device and other technologies, and controlling the temperature of the fuel and the materials of the components in the reactor, so that the high-flux gas cooled reactor technology is realized.

Example 4:

on the basis of embodiment 1, embodiment 2 and embodiment 3, this embodiment further proposes a combined system of a gas cooled reactor and a fusion reactor, as shown in fig. 7, which includes any one of the foregoing gas cooled reactors 100 of embodiment 1, embodiment 2 or embodiment 3, and further includes a fusion reactor 200.

It should be noted that the fusion stack 200 referred to in this application includes all fusion stacks using tritium and/or helium-3 (He-3) as fusion fuel as well as fusion-fission hybrid stacks.

The combined system further comprises a tritium supply system 8, wherein the tritium supply system 8 is connected with the gas-cooled reactor 100 and is also connected with the fusion reactor 200, the gas-cooled reactor 100 produces tritium, and tritium fuel and/or helium-3 fuel is provided for the fusion reactor 200.

The combined system can provide tritium and/or helium-3 as fuel for the fusion reactor or the fusion-fission hybrid reactor by arranging the tritium providing system and collecting, processing, storing, transporting and the like the tritium generated by the gas-cooled reactor in the tritium providing system so as to solve the problems of tritium self-holding and fuel supplementation of the fusion reactor and the fusion-fission hybrid reactor.

Specifically, the tritium supply system 8 comprises a tritium collection system 81, a tritium treatment and storage system 82 and a tritium fuel supplementing system 83 which are sequentially connected, wherein the tritium collection system 81 is communicated with the gas cooled reactor 100, and the tritium fuel supplementing system 83 is communicated with the fusion reactor 200.

Tritium treatment and storage system 82 then 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 a tritium extraction system 821, a tritium purification and separation system 822, and a tritium storage system 823, and monitors the equipment and facilities of each system.

The term "associated" herein refers to the fact that the devices in the tritium monitoring system are physically connected, wirelessly connected, or connected by data transmission, to the devices to be monitored of each subsystem in the tritium processing and storage system 82, thereby implementing different monitoring functions.

Tritium collection system 81 includes: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion/catalysis system; tritium fuel replenishment system 83 includes: a feed pretreatment system and a tritium injection system, the tritium injection system being in communication with the fusion reactor 200. The tritium fuel and helium-3 fuel are separated by the feed pretreatment system and then injected into the fusion reactor 200 by the tritium injection system.

As shown in FIG. 7, the input of the tritium collection system 81 communicates 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.

Further, the input of the tritium collecting system 81 is communicated with the reactor core 1 of the gas cooled reactor 100, reactor coolant in the reactor core 1 enters the tritium providing system 8, and the reactor coolant after separation, purification and tritium removal is returned to the gas cooled reactor 100 for reuse.

The integrated system is communicated with the tritium production module system of the gas cooled reactor and the reactor core through the input of the tritium collection system, when tritium extraction or tritium purification is not needed for the reactor core coolant, the communication between the tritium production module system and the tritium collection system can be only started, and the reactor coolant after tritium removal through separation and purification can be returned to the gas cooled reactor for reuse, so that the economical efficiency is improved.

The present combined system further comprises a bi-directional supply of fissile fuel 9 comprising a first nuclear fuel supply 91 and a second nuclear fuel supply 92, the gas cooled reactor 100 and the fusion reactor 200 providing nuclear fuel to each other via the bi-directional supply of fissile fuel 9. The nuclear fuel herein may include fissile fuel, transfer fuel, fusion fuel, or the like.

Specifically, the gas cooled reactor 100 provides one or more of the following to the fusion reactor 200 via the first nuclear fuel supply system 91: depleted uranium, th-232, U-238 and Pu-239 initial fuels. These materials may be used as a switching fuel for fusion reactors or fissile material for fusion-fission reactors, etc.

The fusion stack 200 provides Pu-239 and/or U-233 to the gas cooled stack 100 via the second nuclear fuel supply system 92. Pu-239 here is used as MOX fuel for gas cooled stacks.

Specifically, the first nuclear fuel supply system 91 includes a spent fuel receiving and dissolving unit, a spent fuel and isotope separation and purification unit, a nuclide extraction unit, a fusion reactor, or a mixed reactor nuclear fuel manufacturing unit, which are sequentially connected.

The second nuclear fuel supply system 92 includes a nuclear fuel cladding receiving and decomposing unit, a cladding shearing decomposing unit, a nuclide separating and purifying unit, and a gas cooled reactor nuclear fuel manufacturing unit, which are sequentially connected.

The first and second nuclear fuel supply systems 91 and 92 each further include a radioactive waste treatment storage unit and a tritium enrichment unit, and the high tritium-containing waste liquid and waste gas generated by the radioactive waste treatment storage unit and the tritium in the tritium enrichment unit are transported to a tritium collection system or a tritium treatment and storage system.

The combined system is provided with the fission fuel bidirectional supply system, so that the gas-cooled reactor and the fusion reactor in the combined system can mutually supply nuclear fuel, the aim of symbiosis of the gas-cooled reactor and the fusion reactor or the fusion fission mixed reactor is fulfilled, the utilization rate of the fission fuel is increased, the total radioactive waste is reduced, and the economical efficiency of the combined system is enhanced.

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

2. The combined system is provided with the fission fuel bidirectional supply system, so that the gas-cooled reactor and the fusion reactor in the combined system can mutually supply nuclear fuel, the aim of symbiosis of the gas-cooled reactor and the fusion reactor or the fusion fission mixed reactor is fulfilled, the utilization rate of the fission fuel is increased, the total radioactive waste is reduced, and the economical efficiency of the combined system is enhanced.

The above description is only of the preferred embodiments of the present invention and is not intended to limit the present invention, but various modifications and variations can be made to the present invention by those skilled in the art. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present invention should be included in the protection scope of the present invention.

Claims

1. A gas cooled reactor comprising a core (1), a nuclear fuel containment barrier (3) and a reactor pressure vessel (5) disposed radially from inside to outside of the gas cooled reactor (100), characterized in that: the reactor comprises a reactor core (1), a nuclear fuel seal isolation layer (3) and a reactor pressure vessel (5), and a tritium production module system (4), wherein the tritium production module system (4) is positioned at the periphery of the reactor core (1), and is positioned between the nuclear fuel seal isolation layer (3) and the reactor pressure vessel (5), and the tritium production module system (4) comprises tritium proliferation materials, and the tritium proliferation materials react with neutrons generated by the reactor core (1) to generate tritium elements.

2. A gas cooled reactor as in claim 1, wherein: the gas cooled reactor (100) comprises a reactor coolant inlet, a first gas accelerating device (6) is arranged at the reactor coolant inlet, and a gas medium physical parameter adjusting system (61) is arranged on the first gas accelerating device (6).

3. A gas cooled reactor as claimed in claim 2, wherein: the gas medium physical parameter adjusting system (61) comprises a plurality of connecting pipelines (62) and valve assemblies, a plurality of holes are formed in the wall surface of the air inlet section of the first gas accelerating device (6) and are respectively communicated with the plurality of connecting pipelines (62), the valve assemblies are arranged on the plurality of connecting pipelines (62), and the valve assemblies comprise adjusting valves, constant pressure check valves and/or variable pressure check valves.

4. A gas cooled reactor according to claim 3, wherein: the reactor coolant inlet is respectively communicated with the reactor core (1) and the tritium production module system (4), the gas cooled reactor (100) comprises a splitter plate (7), the splitter plate (7) is positioned between the first gas accelerating device (6) and the reactor core (1) and also positioned between the first gas accelerating device (6) and the tritium production module system (4), and the splitter plate (7) isolates the reactor coolant entering the reactor core (1) from the reactor coolant entering the tritium production module system (4).

5. A gas cooled reactor as set forth in claim 4, wherein: 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 accelerating device (41);

by adjusting the space between the diverter plate (7) and the reactor pressure vessel (5), the amount and parameters of the intake air of the reactor coolant entering the second gas accelerator (41) are adjusted, and the reactor coolant entering the tritium producing module system (4) is coupled with the second gas accelerator (41).

6. A gas cooled reactor as set forth in claim 5, wherein: the first gas accelerating device (6) and/or the second gas accelerating device (41) are/is provided with a sectional area changing structure, and the sectional area changing structure comprises a contraction section or a contraction section, a narrow throat section and an expansion section which are sequentially connected along the gas flowing direction, wherein the sectional area of the contraction section is changed from large to small along the flowing direction, and the sectional area of the expansion section is changed from small to large along the flowing direction.

7. A gas cooled reactor according to any one of claims 1-6, wherein: the tritium producing module system (4) further comprises cladding (42) and tritium producing layer groups, the cladding (42) are arranged along the radial interval of the gas cooled reactor (100), the tritium producing layer groups are located between the cladding (42), the tritium producing layer groups comprise tritium proliferation layers (44) and/or tritium proliferation multiplication layers (45), the tritium proliferation layers (44) and the tritium proliferation multiplication layers (45) comprise tritium producing areas, and the tritium producing areas comprise tritium proliferation materials.

8. A gas cooled reactor as set forth in claim 7, wherein: the tritium-producing layer group further comprises a tritium pipeline (46) for circulating the reactor coolant and the tritium-containing medium, the tritium pipeline (46) extends along the axial direction of the gas cooled reactor (100), and a plurality of holes are formed in the pipe wall of the tritium pipeline (46) so that the inside of the tritium pipeline (46) is in fluid communication with the tritium-producing region.

9. A gas cooled reactor as set forth in claim 8, wherein: the tritium producing layer group comprises a first neutron multiplication layer (43) and a tritium multiplication layer (44) which are radially arranged along the gas cooled reactor (100), the tritium multiplication layer (44) is located on the outer side of the first neutron multiplication layer (43), the first neutron multiplication layer (43) comprises neutron multiplication materials, and the tritium pipeline (46) is located at least partially in the tritium multiplication layer (44).

10. A gas cooled reactor as in claim 9, wherein: the tritium-producing module system (4) further comprises a partition board (47), wherein the partition board (47) is arranged between layers of different types in the tritium-producing layer group and/or between the tritium-producing layer group and other layers; the tritium-producing module system (4) further comprises a tritium-preventing layer, the tritium-preventing layer is adjacent to the cladding (42), the tritium-preventing layer comprises an oxide and titanium-containing ceramic, and the oxide comprises one or more of the following substances: cr (Cr) ₂ O ₃ 、Al ₂ O ₃ 、Ti ₂ O ₂ 。

11. A gas cooled reactor as in claim 10, wherein: the tritium producing module system (4) further comprises a radiation product producing layer (49), the material of the radiation product producing layer (49) comprising one or more of the following: np-237 and its compounds for producing Pu-238, co-59 and its compounds for producing Co-60; the baffles (47) are arranged on two sides of the irradiation product production layer (49), and the irradiation product production layer (49) is positioned on the outer side of the tritium proliferation layer (44).

12. A gas cooled reactor as set forth in claim 11, wherein: the tritium-producing module system (4) further comprises a first reflecting layer or a first moderating layer (48), wherein the first reflecting layer or the first moderating layer (48) is positioned outside the irradiation product production layer (49), and the material of the first reflecting layer or the first moderating 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. A gas cooled reactor as set forth in claim 8, wherein: the tritium producing layer group comprises a tritium multiplication layer (45), the tritium multiplication layer (45) comprises a neutron multiplication part (451) and a cylindrical tritium multiplication part (452), a plurality of tritium multiplication parts (452) are uniformly arranged in the neutron multiplication part (451), the volume ratio of the neutron multiplication part (451) to the tritium multiplication part (452) is in the range of 2:1 to 8:1, and the tritium pipelines (46) are arranged in an array in the tritium multiplication part (452).

14. A gas cooled reactor as set forth in claim 6, wherein: the reactor core (1) comprises a fuel assembly (11), the fuel assembly (11) is divided into a plurality of sections along the axial direction of the gas cooled reactor (100), and the enrichment degree of the fissionable nuclide of the fuel assembly (11) is increased section by section from the air inlet end to the air outlet end of the fuel assembly (11).

15. A gas cooled reactor as in claim 14, wherein: the fuel assembly (11) is divided into 3-8 sections along the axial direction of the gas cooled reactor (100), and the fuel assembly (11) adopts fuels with 3-4 different enrichment degrees and easy fissile nuclides.

16. A gas cooled reactor as in claim 15, wherein: the fuel assembly (11) comprises a fuel assembly coolant flow passage, a third gas accelerating device (12) is arranged on the fuel assembly coolant flow passage, and the third gas accelerating device (12) adopts a structure with a variable sectional area and comprises a contraction section or the contraction section, the narrow throat section and the expansion section which are sequentially connected along the gas circulation direction.

17. A gas cooled reactor as in claim 16, wherein: the whole fuel assembly (11) is cylindrical and is divided into multiple layers along the radial direction of the gas cooled reactor (100), and the fuel assembly coolant flow channels comprise interlayer flow channels which are gaps of 2-20 mm between different layers of the fuel assembly (11); the fuel assembly (11) is further divided into a plurality of sectors along the circumferential direction of the gas cooled reactor (100), so that each layer of the fuel assembly (11) is provided with a plurality of fuel elements (13), the fuel assembly coolant flow passage further comprises an axial duct, and each fuel element (13) is provided with a plurality of axial ducts along the axial direction of the gas cooled reactor (100).

18. A gas cooled reactor as set forth in claim 17, wherein: the number of axial channels on each fuel element (15) is determined according to the following formula:wherein n is the number of the axial pore channels, 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 reactor from inside to outside.

19. A gas cooled reactor according to any one of claims 14 to 18, wherein: the gas cooled reactor (100) is a high flux gas cooled reactor or a high flux gas cooled fast reactor, and the thermal neutron fluence rate of the tritium producing module system (4) of the high flux gas cooled reactor is 1.0 multiplied by 10 ¹¹ ～5.0×10 ¹⁵ n/cm ² S, the fast neutron fluence rate is 1.5X10 ¹⁰ ～1.0×10 ¹⁵ n/cm ² S; the thermal neutron fluence rate of the tritium-producing module system (4) of the high flux gas cooled fast reactor is 1.0 multiplied by 10 ¹¹ ～5.0×10 ¹⁵ n/cm ² S, the fast neutron fluence rate is 3X 10 ¹² ～5.0×10 ¹⁵ n/cm ² ·s。

20. A gas cooled reactor as in claim 19, wherein: the high-flux gas cooled reactor and the high-flux gas cooled fast reactor adopt uranium fuel or uranium thorium MOX fuel, wherein the enrichment degree of U-235 is not lower than 15%; if uranium plutonium MOX fuel, thorium plutonium MOX fuel or uranium thorium plutonium MOX fuel is used, the enrichment degree of Pu-239 is not less than 10%.

21. A gas cooled reactor according to any one of claims 8-13, wherein: a coolant flow channel and/or a second neutron multiplication layer and/or a second reflection layer and/or a second slowing layer are arranged between the nuclear fuel sealing isolation layer (3) and the tritium production module system (4); 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. A gas cooled reactor as set forth in claim 21, wherein: the nuclear fuel seal isolation layer (3) comprises a metal container or a coaming, and further comprises a fixed supporting member, a neutron adjusting layer (2) is arranged between the reactor core (1) and the nuclear fuel seal isolation layer (3), and the neutron adjusting layer (2) comprises a coolant flow channel and/or a fourth neutron multiplication layer and/or a fourth reflection layer and/or a fourth slowing-down layer.

23. A gas cooled reactor as in claim 22, wherein: the thermal neutron fluence rate of the tritium-producing module system (4) of the gas cooled reactor (100) is 1.0X10 ¹⁰ ～2.0×10 ¹³ n/cm ² S, the fast neutron fluence rate is 5.0X10 ⁹ ～5.0×10 ¹² n/cm ² S; if the gas cooled reactor (100) is a gas cooled fast reactor, the thermal neutron fluence rate of the tritium production module system (4) is 1.0 multiplied by 10 ¹⁰ ～2.0×10 ¹³ n/cm ² S, the fast neutron fluence rate is 5.0X10 ⁹ ～1.0×10 ¹³ n/cm ² ·s。

24. A gas cooled reactor as in claim 20, wherein: the gas cooled reactor (100) and the gas cooled fast reactor adopt the uranium fuel or the uranium thorium MOX fuel, wherein the enrichment degree of U-235 is not lower than 4.5%; if the uranium plutonium MOX fuel, the thorium plutonium MOX fuel or the uranium thorium plutonium MOX fuel is adopted, the enrichment degree of Pu-239 is not lower than 5%.

25. A gas cooled reactor and fusion reactor combination system, characterized by: comprising the fusion stack (200), further comprising the gas cooled stack (100) according to any one of claims 1-24, the fusion stack (200) comprising various fusion stacks fuelled with tritium and/or helium-3 and fusion-fission hybrid stacks;

the combined system further comprises a tritium supply system (8), wherein the tritium supply system (8) is connected with the gas cooled reactor (100) and is also connected with the fusion reactor (200), the gas cooled reactor (100) is used for producing tritium, and tritium fuel and/or helium-3 fuel is supplied to the fusion reactor (200) through the tritium supply system (8).

26. The combination of claim 25, wherein: the tritium supply system (8) comprises a tritium collection system (81), a tritium treatment and storage system (82) and a tritium fuel supplementing system (83) which are sequentially connected, wherein the tritium collection system (81) is communicated with the gas cooled reactor (100), and the tritium fuel supplementing system (83) is communicated with the fusion reactor (200).

27. The combination of claim 26, wherein: the tritium treatment 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 equipment and facilities in each system.

28. The combination of claim 27, wherein: 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 feed pretreatment system and a tritium injection system.

29. The combination of claim 26, wherein: the input of the tritium collection system (81) is communicated with the tritium production module system (4) of the gas cooled reactor (100), and reactor coolant and tritium-containing medium in the tritium production module system (4) enter the tritium supply system (8).

30. The combination of claim 29, wherein: the input of the tritium collecting system (81) is communicated with the reactor core (1) of the gas-cooled reactor (100), the reactor coolant in the reactor core (1) enters the tritium providing system (8), and the reactor coolant after separation, purification and tritium removal is returned to the gas-cooled reactor (100) for reuse.

31. The combination of claim 25, wherein: the combined system further comprises a fission fuel bi-directional supply system (9) comprising a first nuclear fuel supply system (91) and a second nuclear fuel supply system (92), the gas cooled reactor (100) providing one or several of the following to the fusion reactor (200) through the first nuclear fuel supply system (91): depleted uranium, th-232, U-238 and Pu-239 initial fuels.

32. The combination of claim 31, wherein: the fusion stack (200) provides Pu-239 and/or U-233 to the gas cooled stack (100) via the second nuclear fuel supply system (92).