CN116759114A - Tritium production module system, gas cooled reactor and tritium system - Google Patents

Tritium production module system, gas cooled reactor and tritium system Download PDF

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Publication number
CN116759114A
CN116759114A CN202310827029.6A CN202310827029A CN116759114A CN 116759114 A CN116759114 A CN 116759114A CN 202310827029 A CN202310827029 A CN 202310827029A CN 116759114 A CN116759114 A CN 116759114A
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China
Prior art keywords
tritium
layer
multiplication
module system
reactor
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CN202310827029.6A
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Chinese (zh)
Inventor
田英男
米爱军
李晓静
张成龙
赵秋娟
王雅霄
申静怡
贺楷
胡小利
常叶笛
谢思洋
朱宇琛
王晓霞
王炳衡
高桂玲
邱林
王晓亮
杨德锋
陈宗欢
刘雪凇
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China Nuclear Power Engineering Co Ltd
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China Nuclear Power Engineering Co Ltd
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Application filed by China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Priority to CN202310827029.6A priority Critical patent/CN116759114A/en
Publication of CN116759114A publication Critical patent/CN116759114A/en
Pending legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21B—FUSION REACTORS
    • G21B1/00—Thermonuclear fusion reactors
    • G21B1/01—Hybrid fission-fusion nuclear reactors
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21B—FUSION REACTORS
    • G21B1/00—Thermonuclear fusion reactors
    • G21B1/11—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/18—Apparatus for bringing fuel elements to the reactor charge area, e.g. from a storage place

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)

Abstract

The invention discloses a tritium-producing module system in a reactor, which is provided with a multilayer structure distributed along the radial direction of the reactor, wherein the tritium-producing module system comprises a tritium-producing region and a circulating region, the tritium-producing region comprises a tritium proliferation material, and the tritium proliferation material reacts with neutrons to produce tritium elements; the tritium producing module system is in fluid communication with the outside of the tritium producing module system through the flow-through region; the circulation area comprises a tritium pipeline, the tritium pipeline is used for circulating a reactor coolant and a tritium-containing medium, and the tritium pipeline extends along the axial direction of the reactor; a plurality of holes are formed in the pipe wall of the tritium pipe, and the tritium pipe is in fluid communication with the tritium producing region through the holes, so that the transfer capacity and efficiency of tritium in the tritium producing module system are enhanced.

Description

Tritium production module system, gas cooled reactor and tritium system
Technical Field
The invention relates to the technical field of tritium production of reactors, in particular to a tritium production module system, a gas cooled reactor and a tritium system.
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. Gas cooled reactors have higher core neutron leakage rates, stiffer neutron spectra (high energy neutron ratios), require more fuel loading, higher (fissionable nuclides) enrichment, and create a more severe neutron irradiation environment than water cooled reactors. Neutrons leaking from the core (especially fast neutrons with energies above 0.1MeV and 1.0 MeV) cause irradiation damage to devices such as reactor internals, pressure vessels and the like, and as the cumulative neutron fluence increases, the mechanical properties of these devices will be affected. The key equipment such as the pressure vessel and the like is aged 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 core will also increase the level of radiation outside the reactor, bringing irradiation risk to external personnel and equipment. Therefore, neutron moderating and reflecting materials (such as graphite) are required to be arranged at the core or the periphery of the core of the gas cooled reactor, or the thickness of a shielding body is increased or materials with stronger shielding performance are adopted outside the reactor, but the volume, the quality and the manufacturing cost of the gas cooled reactor are increased.
In order to solve the irradiation hazard of the gas-cooled reactor high core neutron leakage to reactor components and external personnel and equipment, the application provides a method which can add a tritium production module system at the periphery of the gas-cooled reactor core so as to absorb neutrons leaked from the reactor core, produce tritium by utilizing the action of the leaked neutrons and tritium proliferation materials in the peripheral tritium production module system, and reduce the thicknesses of a gas-cooled reactor reflecting layer, a moderating layer and an external shielding body.
Prior art CN115440394a discloses a tritium producing cladding, which comprises a first wall, a sleeve, a neutron multiplier container and a shielding plate, wherein the shielding plate is supported on one side of the vacuum chamber, the neutron multiplier container is supported on one side of the shielding plate far away from the vacuum chamber, the first wall is sleeved outside the neutron multiplier container, the free end of the first wall is fixedly connected to the shielding plate through welding, the sleeve is positioned inside the neutron multiplier container, and a plurality of sleeves are distributed inside the neutron multiplier container at intervals.
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 technical scheme cannot be applied to a gas cooled reactor, and the transfer capability and efficiency of tritium elements in a tritium-producing cladding layer are required to be improved.
In view of the above technical problems, the present invention is particularly directed.
Disclosure of Invention
The invention mainly aims to provide a tritium-producing module system in a reactor, which can enhance the transfer capacity and efficiency of tritium elements in the tritium-producing module system.
In order to achieve the above object, according to one aspect of the present invention, there is provided a tritium producing module system in a reactor, the tritium producing module system having a multi-layer structure distributed along a radial direction of the reactor, the tritium producing module system including a tritium producing region and a circulating region, the tritium producing region including a tritium proliferation material, the tritium proliferation material reacting with neutrons to produce tritium element; the tritium producing module system is in fluid communication with the outside of the tritium producing module system through the flow-through region; the circulation area comprises a tritium pipeline, the tritium pipeline is used for circulating a reactor coolant and a tritium-containing medium, and the tritium pipeline extends along the axial direction of the reactor; a plurality of holes are formed in the pipe wall of the tritium pipe, and the tritium pipe is in fluid communication with the tritium producing area through the holes.
Further, the tritium pipeline is a multi-layer pipeline, and a plurality of holes are formed in any layer of the multi-layer pipeline or on the wall of any multi-layer pipeline.
Further, the tritium pipeline is a 2-3-layer pipeline, holes are formed in the pipe wall of each layer of pipeline, and the number of the holes is increased layer by layer from the outer layer to the inner layer of the tritium pipeline.
Further, the tritium producing module system includes a coolant inlet including a fluid accelerating device in communication with the tritium conduit.
Further, the fluid accelerating device is of a structure with a variable sectional area, the fluid accelerating device comprises a contraction section, or a contraction section, a narrow throat section and an expansion section which are sequentially connected along the flowing direction, 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 reactor, the tritium-producing layer groups are positioned between the cladding, the tritium-producing layer groups comprise tritium proliferation layers and/or tritium proliferation multiplication layers, and the tritium pipeline is at least partially positioned in the tritium-producing layer groups.
Further, the tritium producing layer group comprises a neutron multiplication layer and a tritium multiplication layer which are arranged along the radial direction of the reactor, the tritium multiplication layer is positioned on the outer side of the neutron multiplication layer, 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, and the partition board is positioned between different types of layers in the tritium-producing layer group; the tritium-producing module system further comprises a tritium-preventing permeation layer, the tritium-preventing permeation layer is adjacent to the cladding, a coating or low-permeation structure is adopted, 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 reflecting layer or a slowing layer, wherein the material of the reflecting layer or the 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 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 compound for producing Pu-238, co-59 and its compound for producing Co-60, and spacers are provided on both sides of the production layer of the irradiated product.
Further, the tritium-producing module system comprises an cladding, a tritium-preventing permeation layer, a neutron multiplication layer, a partition plate, a tritium proliferation layer, a partition plate, a radiation product production layer, a partition plate, a reflecting layer or a slowing layer, a tritium-preventing permeation layer and a cladding which are sequentially arranged from inside to outside along the radial direction of the reactor.
Further, the tritium-producing layer group comprises a first circulating structure, wherein in the first circulating structure, a neutron multiplication layer and a tritium multiplication layer which are arranged along the radial direction of the reactor circulate for a plurality of times; or the tritium-producing layer group comprises a second circulation structure, and in the second circulation structure, the neutron multiplication layer, the tritium multiplication layer and the tritium multiplication layer which are arranged along the radial direction of the reactor are arranged in any combination for multiple times.
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, the plurality of tritium multiplication parts are uniformly arranged in the neutron multiplication part, and the volume ratio of the neutron multiplication part to the tritium multiplication part is 2:1 to 8: within the range of 1, tritium pipelines are arranged in an array in a tritium proliferation part.
Further, the tritium producing module system is in a circular column shape and completely surrounds the periphery of the reactor core in the circumferential direction, and is formed by splicing a plurality of tritium producing submodules in the circumferential direction, wherein the number of the tritium producing submodules is in the range of 4-24.
Further, the neutron multiplication layer comprises neutron multiplication material balls, neutron multiplication materials are arranged in the neutron multiplication material balls, and the neutron multiplication materials comprise beryllium and beryllium-containing compounds; the tritium proliferation layer 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 a plurality 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.
Further, the tritium multiplication layer comprises neutron multiplication material balls and tritium multiplication material balls; or the tritium multiplication layer comprises a tritium multiplication material ball, the tritium multiplication material ball is provided with a tritium multiplication material at the ball center part, and the tritium multiplication material ball is provided with a neutron multiplication material at the ball shell part.
Further, the enrichment degree of Li-6 in the tritium proliferation material is 7.5% -90%, the enrichment degree of Li-7 is 10% -92.5%, and the total enrichment degree of Li-6 and Li-7 is 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.
Further, the neutron multiplication layer, the tritium multiplication layer and the tritium multiplication layer all comprise tritium production layer group air inlets, and the tritium production layer group air inlets are provided with a supporting structure and a first filter screen for preventing materials in the tritium production layer group from leaking.
Further, a second filter screen or a filter membrane is arranged on the inner side or the outer side of the pipe wall of the tritium pipe so as to prevent materials or dust in the tritium producing layer group from entering the tritium pipe. By applying the technical scheme of the invention, at least the following beneficial effects are realized:
1. according to the tritium production module system, the fluid accelerating device is arranged at the coolant inlet, so that the flow rate of tritium medium contained in the tritium production module system can be improved, the flow rate, the pressure and the density of gas mediums entering different structural layers of the tritium production module system are different, the capability and the efficiency of carrying tritium by the gas mediums are enhanced, and simultaneously, the generated ultrasonic fluctuation can remove the tritium deposited and attached on the wall of a flow channel in the tritium production module system, so that the sedimentation loss of the tritium is reduced.
2. According to the tritium production module system, the tritium pipelines are arranged to be multiple layers, holes are formed in the pipe wall, and the number of the holes is set, so that tritium elements are easier to release and diffuse into the tritium pipelines from the tritium production module system, and through the communication cooperation of the tritium pipelines and the fluid accelerating device, the air flow rate of the tritium pipelines from the outer layer to the inner layer is increased layer by layer, the pressure is reduced layer by layer, and the release and diffusion efficiency of tritium from the tritium production area to the tritium pipelines is further enhanced.
3. The tritium production module system can better realize the functions of neutron multiplication and tritium element generation by arranging the neutron multiplication layer, the tritium multiplication layer structure or the tritium multiplication layer structure, and improves the tritium production rate by distributing positions of different abundance of Li-6 and Li-7; tritium is produced by utilizing the gas cooled reactor, so that the irradiation hazard of neutron leakage of a high reactor core of the gas cooled reactor to reactor components, external personnel and equipment is solved, and the thicknesses of a gas cooled reactor reflecting layer, a moderating layer and an external shielding body can be reduced.
4. According to the tritium production module system, the support structure and the first filter screen are arranged at the gas inlet of the tritium production layer group, so that gas medium can enter and materials in the tritium production module system can be prevented from leaking out; by arranging the second filter screen or the filter membrane on the inner side or the outer side of the pipe wall of the tritium pipe, materials or dust in the tritium production layer group are prevented or reduced from entering the tritium pipe, and graphite dust and other impurities of the reactor core are also prevented from entering the tritium production module system.
5. 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.
In order to achieve the above object, according to still another aspect of the present invention, a gas cooled reactor is provided, which includes a tritium producing module system disposed at the periphery of the core of the gas cooled reactor, and the tritium producing module system reacts with neutrons of the core to produce tritium.
Further, the gas cooled reactor comprises a reactor core, a nuclear fuel seal isolation layer and a reactor pressure vessel which are arranged along the radial direction of the gas cooled reactor from inside to outside, and the tritium producing module system is positioned between the nuclear fuel seal isolation layer and the reactor pressure vessel.
Further, the nuclear fuel seal barrier comprises a metal container or shroud and also comprises a fixed support member.
Further, the gas cooled reactor further comprises a neutron regulating layer, wherein the neutron regulating layer comprises a first neutron regulating layer, a second neutron regulating layer and a third neutron regulating layer, and the neutron regulating layer comprises a coolant flow channel and/or a neutron multiplication layer and/or a reflecting layer and/or a slowing-down layer.
Further, a second neutron regulating layer is arranged between the nuclear fuel sealing isolation layer and the tritium producing module system.
Further, a third neutron regulating layer is arranged between the reactor pressure vessel and the tritium production module system.
Further, a first neutron modifying layer is disposed between the core and the nuclear fuel containment barrier.
By applying the technical scheme of the application, at least the following beneficial effects are realized:
1. the gas cooled reactor provided by the application can solve the problem that radiation damage to reactor components, external personnel and equipment is caused by neutron leakage of a high reactor core of the gas cooled reactor, and can reduce the thicknesses of a gas cooled reactor reflecting layer, a moderating layer and an external shielding body by arranging the tritium producing module system at the periphery of the reactor core to produce tritium elements.
2. According to the gas cooled reactor provided by the application, the neutron adjusting layers are arranged on the two sides of the tritium producing module system and between the reactor core and the nuclear fuel sealing isolation layer, so that the utilization rate of neutrons in the reactor core in the gas cooled reactor can be improved, and the tritium producing efficiency can be improved; by changing the neutron regulating layer structure, the gas cooled reactor with different types and different states can be adapted.
In order to achieve the above object, according to a further aspect of the present application, there is provided a tritium system, comprising a tritium producing module system, and further comprising a tritium fuel supply system, wherein the tritium producing module system is connected with the tritium fuel supply system, and a reactor coolant and a tritium-containing medium in the tritium producing module system are input into the tritium fuel supply system to obtain tritium and/or helium-3 fuel, and the tritium fuel and/or helium-3 fuel is delivered to a fusion reactor.
Further, the tritium fuel supply system comprises a tritium collection system, a tritium treatment storage system and a tritium supplementing system which are sequentially connected, wherein the tritium collection system is connected with the tritium production module system, and the tritium supplementing system is connected with the fusion reactor.
Further, the tritium treatment storage system includes: the system comprises a tritium extraction system, a tritium purification and separation system, a tritium storage system and a tritium monitoring system, wherein the tritium monitoring system is respectively associated with the tritium extraction system, the tritium purification and separation system and the tritium storage system and monitors equipment and facilities of each system.
Further, the tritium collection system includes: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion/catalysis system.
Further, the tritium replenishment system comprises: a feed pretreatment system and a tritium injection system.
By applying the technical scheme of the application, at least the following beneficial effects are realized: the tritium system provided by the application can be used for conveying tritium and/or helium-3 fuel to the fusion reactor by arranging the tritium fuel supply system connected with the tritium production module system, collecting, processing, storing, transporting and the like the tritium produced in the tritium production module system in the tritium fuel supply system, so as to solve the problems of self-holding and fuel supplementation of the fusion reactor.
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 partial cross-sectional view of a tritium-producing module system in example 1 of this invention;
FIG. 2 is a schematic diagram showing the flow of tritium-containing medium in the tritium-producing module system of example 1 of this invention;
FIG. 3 shows a schematic cross-sectional view of a reactor in example 1 of the present invention;
FIG. 4 shows a schematic cross-sectional view of a reactor in example 2 of the present invention;
FIG. 5 shows a schematic diagram of a tritium system in example 3 of the present invention.
Wherein the above figures include the following reference numerals:
1. a tritium pipe; 2. a hole; 3. a fluid accelerating device; 4. a cladding; 5. a neutron multiplication layer; 6. a tritium proliferation layer; 7. a tritium multiplication layer; 8. a first filter screen; 9. a partition plate; 10. a slowing layer; 11. irradiating a production layer of the product; 12. a neutron multiplication unit; 13. a tritium proliferation section; 14. a core; 15. a first neutron modifying layer; 16. a nuclear fuel seal and isolation layer; 17. a reactor pressure vessel; 18. a tritium fuel supply system; 19. a tritium collection system; 20. a tritium treatment storage system; 21. a tritium replenishment system; 22. a tritium extraction system; 23. a tritium purification and separation system; 24. a tritium storage system; 25. a gas cooled reactor; 26. 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 invention will be understood in specific cases by those of ordinary skill in the art. Furthermore, in the description of the present invention, unless otherwise indicated, the meaning of "a plurality" is two or more.
In both embodiments 1 and 2 of the present application, the gas-cooled reactor is taken as an example, and the structural shape and the like of the tritium-producing module system disposed inside the gas-cooled reactor are shown, which are only preferred, and in other embodiments, the tritium-producing module system may be used for a pressurized water reactor, a heavy water reactor, a fast neutron reactor, and the like.
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 releasing and diffusing 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.
Tritium is produced by utilizing the gas cooled reactor, so that the irradiation hazard of neutron leakage of a high reactor core of the gas cooled reactor to reactor components, external personnel and equipment is solved, and the thicknesses of a gas cooled reactor reflecting layer, a moderating layer and an external shielding body can be reduced.
Example 1:
the invention provides a tritium producing module system in a reactor, which is shown in fig. 1 and has a multi-layer structure distributed along the radial direction of the reactor, wherein the tritium producing module system comprises a tritium producing region and a circulating region, the tritium producing region comprises a tritium proliferation material, the tritium proliferation material reacts with neutrons to generate tritium elements, and the tritium producing module system is in fluid communication with the outside of the tritium producing module system through the circulating region.
Specifically, the circulation area comprises a tritium pipeline 1, wherein the tritium pipeline 1 is used for circulating a reactor coolant and a tritium-containing medium, and is mainly used for guiding tritium elements generated in the tritium-producing area out of a tritium-producing module system. The tritium pipeline 1 extends along the axial direction of the reactor, a plurality of holes 2 are formed in the pipe wall of the tritium pipeline 1, and the tritium pipeline 1 is in fluid communication with a tritium producing region through the holes 2.
Tritium conduit 1 is a single or multi-layer conduit. Preferably, the tritium pipeline 1 is a multi-layer pipeline, and a plurality of holes 2 are formed in any layer of the multi-layer pipeline or any pipe wall of the multi-layer pipeline. Further preferably, referring to fig. 1, the tritium pipeline 1 is a 2-3 layer pipeline, holes 2 are formed in the pipe wall of each layer of pipeline, and the number of the holes 2 is increased layer by layer or the size of the holes 2 is increased layer by layer from the outer layer to the inner layer of the tritium pipeline 1. The pressure of the tritium pipeline is reduced layer by layer from the outer layer to the inner layer, and the air flow rate is increased layer by layer, so that the release and diffusion efficiency of tritium from a tritium production area to the tritium pipeline is further enhanced.
Preferably, the holes 2 can be arranged at intervals along the extension direction of the tritium pipe, and the shape of the holes can be various shapes such as a circle, a square, and the like. In addition, along the extending direction of the tritium pipeline 1, the positions of the holes 2 on the pipe walls of any two adjacent layers of pipelines on the tritium pipeline 1 can be the same or can be staggered. The tritium production module system is characterized in that the tritium pipeline is arranged to be multiple layers, holes are formed in the pipe wall, the size, the number and the positions of the holes are arranged, and the like, so that tritium elements are easier to release and diffuse into the tritium pipeline from the tritium production module system.
In the present application, as shown in FIGS. 1 and 2, the tritium producing module system includes a coolant inlet including a fluid acceleration device 3, the coolant inlet being in communication with a tritium conduit 1. Preferably, the fluid accelerating device 3 is communicated with the tritium pipeline 1, and the fluid accelerating device 3 is communicated and matched with the tritium pipeline 1, so that the flow speed, the pressure and the density of gas mediums entering different structural layers of the tritium production module system are different, and the tritium carrying capacity and the tritium carrying efficiency of the gas mediums in the tritium pipeline 1 are enhanced.
Specifically, the fluid accelerator 3 is configured to have a cross-sectional area varying, and is not limited to a tubular structure having a cross-sectional area varying, a plate-like structure, or the like. The fluid accelerating device 3 comprises a contraction section, a narrow throat section and an expansion section which are sequentially connected along the flowing direction, 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 fluid accelerating device 3 is a laval nozzle or a laval nozzle-like structure designed by using the Bernoulli principle and related physics principle, and can accelerate gas to supersonic speed under certain conditions. Furthermore, in other embodiments, the fluid accelerating device 3 may comprise only a constriction section, and may also function to accelerate the gas.
Specifically, referring to the trend of the air flow in the tritium producing module system shown in fig. 2, the tritium producing module system can improve the flow rate of tritium medium in the tritium producing module system by arranging the fluid accelerating device at the coolant inlet, so that the flow rate, the pressure and the density of the gas medium entering different structural layers of the tritium producing module system are different, and the capability and the efficiency of carrying tritium by the gas medium are enhanced. Simultaneously, the generated ultrasonic wave can remove the tritium deposited and attached on the pipe wall of the runner and in the tritium producing module system, thereby reducing the sedimentation loss of the tritium. In addition, through the communication between the fluid accelerating device and the tritium pipeline and the design of the number and the size of the holes on the pipe wall of each layer of tritium pipeline, the flow rate of the tritium pipeline from the outside to the inner layer is increased layer by layer, and the pressure is reduced layer by layer, so that the release and diffusion efficiency of the tritium from the tritium producing area to the tritium pipeline is further enhanced.
As shown in fig. 3, in the present embodiment, the gas cooled reactor includes a gas cooled reactor core 14, a first neutron modifying layer 15, a nuclear fuel containment barrier layer 16, and a reactor pressure vessel 17 disposed radially from inside to outside. Wherein the tritium producing module system is located between the nuclear fuel seal isolation layer 16 and the reactor pressure vessel 17. Wherein the first neutron modifying layer 15 may be provided as a coolant flow channel and/or neutron multiplying layer and/or reflecting layer and/or moderating layer. The nuclear fuel seal and spacer layer 16 comprises a metal container or shroud and also includes a stationary support member.
The neutron regulating layer is included in the gas cooled reactor, so that the energy and the quantity of the neutrons can be regulated, and the tritium production efficiency of the tritium production module system can be improved. The neutron modifying layers include a first neutron modifying layer 15, and second and third neutron modifying layers. Coolant flow channels and/or neutron multiplication layers and/or reflection layers and/or moderation layers may be provided as desired in each of the neutron modifying layers.
In the gas cooled reactor, a second neutron modifying layer may be disposed between the nuclear fuel containment layer 16 and the tritium production module system and/or a third neutron modifying layer may be disposed between the reactor pressure vessel 17 and the tritium production module system. According to the gas cooled reactor provided by the application, the neutron adjusting layers are arranged on the two sides of the tritium producing module system and between the reactor core and the nuclear fuel sealing isolation layer, so that the utilization rate of neutrons in the reactor core in the gas cooled reactor can be improved, and the tritium producing efficiency can be improved; by changing the neutron regulating layer structure, the gas cooled reactor with different types and different states can be adapted.
Specifically, the tritium producing module system includes cladding 4 and tritium producing layer groups, with cladding 4 being spaced apart along the reactor radial direction. I.e. the cladding 4 is located at the outermost layer of the tritium-producing module system along the radial direction of the reactor, and the tritium-producing layer group is located between the two cladding 4 layers.
The tritium-producing layer group at least comprises one of a tritium proliferation layer 6 and a tritium proliferation multiplication layer 7, wherein the tritium proliferation layer 6 and the tritium proliferation multiplication layer 7 both comprise a tritium-producing region, and the tritium-producing region comprises a tritium proliferation material.
A neutron multiplication layer 5 can be further arranged in the tritium-producing layer group, and the neutron multiplication layer 5 comprises neutron multiplication materials. Neutron multiplication layer 5 may be co-configured with either or both of tritium multiplication layer 6 and tritium multiplication layer 7. Preferably, neutron multiplication layer 5 is provided simultaneously with only tritium multiplication layer 6 in the tritium producing layer group. Tritium pipeline 1 is located in tritium producing layer group.
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.
Preferably, as shown in FIG. 3, the engineered reactor type employs a gas cooled reactor of a hexagonal prism core. The first neutron regulating layer 15 in the gas cooling pile is provided with a neutron multiplication layer to make the thermal neutron fluence rate of the tritium producing module system of the gas cooling pile be 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。
In the air-cooled fast reactor, a moderating layer can be arranged in the first neutron regulating layer 15, and the thermal neutron fluence rate of the tritium-producing module system 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。
To further increase neutron fluence (rate) at the tritium production module system, the gas cooled stacks can be modified to high flux gas cooled stacks. In the high flux gas cooled reactor, the first neutron regulating layer 15 is provided with a coolant flow channel to enhance the cooling efficiency and make the thermal neutron fluence rate of the tritium producing module system be 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, thereby increasing tritium-generating capacity and efficiency.
The gas cooled reactor can also be modified to a high flux gas cooled fast reactor. In the high flux gas cooled fast reactor, the first neutron regulating layer 15 is provided with a coolant flow passage and a moderating layer or a reflecting layer, and the thermal neutron fluence rate of the tritium producing module system 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。
The core fuel is uranium, thorium and plutonium-containing substances, and comprises: 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. Preferably, the engineering gas cooled reactor core adopts uranium fuel, wherein the minimum enrichment degree of U-235 in the fuel is not less than 4.5%, the maximum enrichment degree is 20%, and the average enrichment degree is not less than 8%; thereby ensuring the neutron fluence (quantity) of the tritium-producing module system and ensuring the tritium-producing quantity.
In order to improve the neutron fluence of the reactor, MOX fuel is adopted in engineering, the enrichment degree of U-235 in the fuel is 0.3%, the minimum enrichment degree of Pu-239 in the fuel is not less than 5%, the maximum enrichment degree is 60%, and the average enrichment degree is 8% -25%.
For the high-flux gas cooled stacks and the high-flux gas cooled fast stacks, if uranium fuel or uranium thorium MOX fuel is adopted, the enrichment degree of U-235 in the fuel is not lower than 15 percent. If uranium plutonium MOX fuel, thorium plutonium MOX fuel or uranium thorium plutonium MOX fuel is used, the enrichment of Pu-239 in the fuel is not less than 10%.
As shown in connection with fig. 1-3, in this embodiment, the tritium producing group comprises a neutron multiplication layer 5 and a tritium multiplication layer 6 arranged radially of the reactor, the tritium multiplication layer 6 being located outside the neutron multiplication layer 5, at least part of the tritium conduit 1 being located within the tritium multiplication layer 6. The neutron multiplication layer 5 is used for multiplying the neutrons, and the tritium multiplication layer 6 is used for enabling the neutrons to react with tritium multiplication materials to generate tritium elements.
The tritium producing module system further comprises a partition plate 9, wherein the partition plate 9 is positioned between different types of layers in the tritium producing layer group, namely, between the neutron multiplication layer 5 and the tritium multiplication layer 6. In other embodiments, the tritium producing layer group comprises a first circulation structure, wherein the neutron multiplication layer 5 and the tritium multiplication layer 6 which are arranged along the radial direction of the reactor circulate for a plurality of times, and a partition plate 9 can be arranged between different layers of the tritium producing layer group. The circulating structure can enhance the utilization rate of neutrons by the tritium production module system.
The tritium-producing module system further comprises a tritium-preventing permeation layer, the tritium-preventing permeation layer is adjacent to the cladding 4, a coating or low-permeation structure is adopted, 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 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.
In addition, the tritium producing module system also includes a reflective or moderating layer 10, the material of the reflective or moderating layer 10 including, but not limited to, 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.
The tritium producing module system also includes a radiation product producing layer 11 for producing a quantity of radiation product, the material of the radiation product producing layer 11 including, but not limited to, one or more of the following: np-237 and its compounds for producing Pu-238, co-59 and its compounds for producing Co-60. Referring to fig. 2, spacers 9 are provided on both sides of the radiation product producing layer 11.
In other embodiments, the irradiation product production layer 11 may be disposed between any two of the neutron multiplication layer, the tritium multiplication layer, the moderation layer 10, or the reflection layer, and the spacers 9 are disposed between the irradiation product production layer and the other layers.
To sum up, in this embodiment, preferably, the tritium producing module system includes an envelope 4, a tritium preventing layer, a neutron multiplication layer 5, a barrier 9, a tritium proliferation layer 6, a barrier 9, a irradiated product producing layer 11, a barrier 9, a reflective layer or a slowing layer 10, a tritium preventing layer, and an envelope 4, which are sequentially arranged from inside to outside in the radial direction of the reactor.
The tritium production module system also includes coolant channels, similar in function to tritium conduit 1, for circulation of reactor coolant and/or tritium-containing medium, the coolant channels being disposed in the interstices between the layers in the tritium production module system, and/or within enclosure 4 and/or barrier 9.
Preferably, the thickness of the envelope and/or separator is greater than 1mm, and if coolant channels are provided in the envelope and/or separator, the thickness of the envelope and/or separator with coolant channels is greater than 3mm.
The tritium producing module system may be completely or partially surrounded by the periphery of the core 14 in the circumferential direction, and the periphery of the core 14 may include a plurality of tritium producing module systems of the same or different structures, and the plurality of tritium producing module systems may be uniformly or unevenly disposed within an angular range of 360 ° or uniformly or unevenly disposed within a partial angular range of the periphery of the 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 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 9 are provided between adjacent tritium producing submodules to prevent direct contact of adjacent tritium producing submodule materials, as shown in fig. 3. The tritium pipeline 1 circumferentially surrounds the reactor core for one circle in the tritium proliferation layer 6, 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.
Preferably, the neutron multiplication layer 5 and the tritium multiplication layer 6 are both in the structure of filling material balls in a ball bed. Wherein the neutron multiplication layer 5 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 6 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 a plurality 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.
In the present application, the enrichment of Li-6 in tritium proliferation material is 7.5% -90%, the enrichment of Li-7 is 10% -92.5%, and the total enrichment of Li-6 and Li-7 is 100%. 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 tritium proliferation materials is finally reduced, and the tritium production rate is improved.
In other embodiments, a tritium multiplication layer can be added into the tritium-producing layer group, the tritium multiplication layer also adopts a structure that material balls are filled in a ball bed, and the tritium multiplication layer comprises neutron multiplication material balls and tritium multiplication material balls; or the tritium multiplication layer comprises a tritium multiplication material ball, the tritium multiplication material ball is provided with a tritium multiplication material at the ball center part, and the tritium multiplication material ball is provided with a neutron multiplication material at the ball shell part.
The tritium-producing layer group can be designed into a second circulation structure, and in the second circulation structure, any permutation and combination of the neutron multiplication layer, the tritium multiplication layer and the tritium multiplication layer which are arranged along the radial direction of the reactor is circulated for one or more times.
As shown in fig. 2, preferably, tritium-producing group gas inlets may be provided at the positions of the neutron multiplication layer and the tritium multiplication layer, and the tritium-producing group gas inlet is provided with a support structure and a first filter screen 8 for enabling a gas medium to enter and preventing materials in the tritium-producing group from leaking out.
In addition, a second filter screen or a filter membrane is arranged on the inner side or the outer side of the pipe wall of the tritium pipe 1 to prevent or reduce materials or dust in the tritium producing layer group from entering the tritium pipe and also prevent graphite dust and other impurities of the reactor core from entering the tritium producing module system.
The first filter screen 8 or the second filter screen may be made of glass fiber, chemical fiber, nano aerogel, and the like, and preferably graphene aerogel.
Example 2:
in comparison with example 1, the position, shape, tritium pipeline, fluid accelerating device 3, filter screen, etc. of the tritium producing module system in the air-cooled reactor in example 2 are substantially the same, except that: as shown in FIG. 4, the tritium producing modular system of example 2 consists of cladding 4 and tritium multiplication layer 7 between the cladding. A tritium-proof layer may also be provided adjacent to the envelope 4.
In this embodiment, tritium multiplication layer 6 and neutron multiplication layer 5 may preferably not be provided in the tritium producing layer group. The tritium multiplication layer 7 in this embodiment includes a neutron multiplication portion 12 and a cylindrical tritium multiplication portion 13, and a plurality of tritium multiplication portions 13 are uniformly arranged in the neutron multiplication portion 12, so that the neutron fluence in each tritium multiplication portion 13 is at the same order of magnitude level. Preferably, a partition plate 9 is provided on the outer periphery of the tritium multiplication section 13 having a cylindrical shape to separate the material of the neutron multiplication section 12 and the tritium multiplication section 13. In the tritium multiplication layer 7, the volume ratio of the neutron multiplication section 12 to the tritium multiplication section 13 is 2: within the range of 1-8:1, tritium pipelines 1 are arranged in an array in a tritium proliferation part 13.
Preferably, the number of tritium breeder sections 13 in each tritium producing submodule is no more than 6, as shown in fig. 4 as 3. So that the distance difference between the material at all positions in the tritium multiplication part 13 and the nearest tritium pipeline 1 is not more than 50% of the diameter of the tritium multiplication part 13, thereby facilitating the release and diffusion of tritium elements in the tritium multiplication part 13.
In other embodiments, the tritium producing layer group includes a second circulation structure in which any permutation and combination of neutron multiplication layer 5, tritium multiplication layer 6, and tritium multiplication layer 7 disposed radially of the reactor are circulated a plurality of times. A spacer 9 may be provided between the different layers. Wherein the neutron multiplication layer 5 and the tritium multiplication layer 6 have the shape and structure as shown in the embodiment 1. The circulation structure has higher utilization rate of neutrons in the reactor.
It should be noted that the structure of the tritium multiplication layer 7 described in this example is merely preferable, and the structure of the tritium multiplication layer 7 is not limited to the form described in fig. 4. For example, the cross-sectional shape of the tritium multiplication section 13 may be another shape, or only a tritium multiplication material pellet may be included in the tritium multiplication layer 7.
In other embodiments, tritium producing layer groups may be provided as a combination of tritium multiplication layer 7 and neutron multiplication layer 5.
Specifically, the tritium multiplication layer 7 may be provided as a mixture of neutron multiplication material pellets and tritium multiplication material pellets. The tritium multiplication layer 7 may also comprise a tritium multiplication material ball, wherein the tritium multiplication material ball is provided with a tritium multiplication material at the spherical center part, and the tritium multiplication material ball is provided with a neutron multiplication material at the spherical shell part.
If the tritium multiplication layer 7 is a mixture of a neutron multiplication material pellet and a tritium multiplication material pellet, for example, the structure of the tritium multiplication layer 7 described in this embodiment has a proportion of 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.
In this embodiment, the irradiation product production layer 11 is preferably not provided. Meanwhile, the neutron multiplication part 12 is used as a neutron reflection layer, and the reflection layer or the slowing-down layer 10 can not be arranged in the tritium producing module system. Thereby greatly simplifying the structure of the tritium-producing module system.
In order to achieve the isotope production, the material in tritium proliferation section 13 may be filled with the isotope production material in an amount not exceeding one-half of the total amount.
In other embodiments, either the radiation product producing layer 11 or the reflective or moderating layer 10 may be provided in the tritium producing module system described in this embodiment.
In summary, from the above description, it can be seen that the two embodiments of the present invention described above achieve the following technical effects:
1. according to the tritium production module system, the fluid accelerating device is arranged at the coolant inlet, so that the flow rate of tritium medium contained in the tritium production module system can be improved, the flow rate, the pressure and the density of gas mediums entering different structural layers of the tritium production module system are different, the tritium carrying capacity and efficiency of the gas mediums are enhanced, and simultaneously, the generated ultrasonic fluctuation can remove tritium deposited and attached to the pipe wall of the flow channel and the tritium production module system, so that the sedimentation loss of tritium is reduced.
2. According to the tritium production module system, the tritium pipelines are arranged to be multiple layers, holes are formed in the pipe wall, and the number of the holes is set, so that tritium elements are easier to release and diffuse into the tritium pipelines from the tritium production module system, and through the communication cooperation of the tritium pipelines and the fluid accelerating device, the air flow rate of the tritium pipelines from the outer layer to the inner layer is increased layer by layer, the pressure is reduced layer by layer, and the release and diffusion efficiency of tritium from the tritium production area to the tritium pipelines is further enhanced.
3. The tritium production module system can better realize the functions of neutron multiplication and tritium element generation by arranging the neutron multiplication layer, the tritium multiplication layer structure or the tritium multiplication layer structure, and improves the tritium production rate by distributing positions of different abundance of Li-6 and Li-7; tritium is produced by utilizing the gas cooled reactor, so that the irradiation hazard of neutron leakage of a high reactor core of the gas cooled reactor to reactor components, external personnel and equipment is solved, and the thicknesses of a gas cooled reactor reflecting layer, a moderating layer and an external shielding body can be reduced.
4. According to the tritium production module system, the support structure and the first filter screen are arranged at the gas inlet of the tritium production layer group, so that gas medium can enter and materials in the tritium production module system can be prevented from leaking out; by arranging the second filter screen or the filter membrane on the inner side or the outer side of the pipe wall of the tritium pipe, materials or dust in the tritium production layer group are prevented or reduced from entering the tritium pipe, and graphite dust and other impurities of the reactor core are also prevented from entering the tritium production module system.
5. 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.
6. The gas cooled reactor provided by the application can solve the problem that radiation damage to reactor components, external personnel and equipment is caused by neutron leakage of a high reactor core of the gas cooled reactor, and can reduce the thicknesses of a gas cooled reactor reflecting layer, a moderating layer and an external shielding body by arranging the tritium producing module system at the periphery of the reactor core to produce tritium elements.
7. According to the gas cooled reactor provided by the application, the neutron adjusting layers are arranged on the two sides of the tritium producing module system and between the reactor core and the nuclear fuel sealing isolation layer, so that the utilization rate of neutrons in the reactor core in the gas cooled reactor can be improved, and the tritium producing efficiency can be improved; by changing the neutron regulating layer structure, the gas cooled reactor with different types and different states can be adapted.
Example 3:
on the basis of the embodiment 1 and the embodiment 2, the application also provides a tritium system, as shown in fig. 5, which comprises any tritium producing module system in any one of the air cooling stacks 25 in the embodiment 1 and the embodiment 2. The tritium system also comprises a tritium fuel supply system 18, wherein the tritium production module system is connected with the tritium fuel supply system 18, and reactor coolant and a tritium-containing medium in the tritium production module system are input into the tritium fuel supply system 18 to obtain tritium and/or helium-3 fuel and are conveyed to the fusion reactor 26.
It should be noted that in the present application, the fusion stack 26 herein includes all fusion stacks fuelled with tritium and/or helium-3 (He-3) as well as fusion fission hybrid stacks.
Specifically, the tritium fuel supply system 18 comprises a tritium collection system 19, a tritium treatment storage system 20 and a tritium replenishment system 21 which are sequentially connected, wherein the tritium collection system 19 is connected with a tritium production module system, and the tritium replenishment system 21 is connected with a fusion reactor 26.
Further, the tritium process storage system 20 includes: the tritium extraction system 22, the tritium purification and separation system 23, the tritium storage system 24 and the tritium monitoring system are respectively associated with the tritium extraction system 22, the tritium purification and separation system 23 and the tritium storage system 24, and key equipment and facilities of each system are monitored.
The term "associated with" herein refers to the fact that the devices in the tritium monitoring system are physically connected, wirelessly connected, or connected by data transmission, etc. to the devices to be monitored in each subsystem in the tritium processing storage system 20, thereby implementing different monitoring functions.
Preferably, the coolant and the tritium-containing medium in the tritium pipeline in the tritium-producing module system are processed and conveyed to the tritium fuel supply system 18 through some accessory equipment in the tritium-producing module system, and after being processed by the tritium collecting system 19 or the tritium purification and separation system 23, the reactor coolant can be returned to the gas-cooled reactor for reuse, so that the economy is improved.
Tritium collection system 19 includes: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion/catalysis system. Tritium replenishment system 21 includes: a feed pretreatment system and a tritium injection system. The tritium injection system injects tritium and/or helium-3 fuel into the fusion reactor 26.
In summary, from the above description, it can be seen that the above embodiments of the present application achieve the following technical effects:
the tritium system provided by the application can be used for conveying tritium and/or helium-3 fuel to the fusion reactor by arranging the tritium fuel supply system connected with the tritium production module system, collecting, processing, storing, transporting and the like the tritium produced in the tritium production module system in the tritium fuel supply system, so that the problem of self-sustaining of the tritium of the fusion reactor is solved, and a foundation is laid for constructing a symbiotic/joint system between the gas cooled reactor and the fusion reactor.
The above description is only of the preferred embodiments of the present application and is not intended to limit the present application, but various modifications and variations can be made to the present application by those skilled in the art. Any modification, equivalent replacement, improvement, etc. made within the spirit and principle of the present application should be included in the protection scope of the present application.

Claims (31)

1. A tritium producing module system arranged inside a reactor, wherein the tritium producing module system is provided with a multi-layer structure distributed along the radial direction of the reactor, the tritium producing module system comprises a tritium producing region and a circulating region, the tritium producing region comprises a tritium proliferation material, and the tritium proliferation material reacts with neutrons to generate tritium elements;
Through the flow-through region, the tritium-producing module system is in fluid communication with an exterior of the tritium-producing module system;
the method is characterized in that: the flow-through region comprises a tritium pipe (1), wherein the tritium pipe (1) is used for the flow-through of a reactor coolant and a tritium-containing medium, and the tritium pipe (1) extends along the axial direction of the reactor;
a plurality of holes (2) are formed in the pipe wall of the tritium pipe (1), and the tritium pipe (1) is in fluid communication with the tritium producing area through the holes (2).
2. The tritium production module system of claim 1, wherein: the tritium pipeline (1) is a multi-layer pipeline, and a plurality of holes (2) are formed in any layer of the multi-layer pipeline or the pipe wall of any multi-layer pipeline.
3. The tritium production module system of claim 2, wherein: the tritium pipeline (1) is a 2-3-layer pipeline, holes (2) are formed in the pipe wall of each layer of pipeline, and the number of the holes (2) is increased layer by layer from the outer layer to the inner layer of the tritium pipeline (1).
4. A tritium producing module system according to any one of claims 1-3, characterized in that: the tritium production module system comprises a coolant inlet, wherein the coolant inlet comprises a fluid accelerating device (3), and the fluid accelerating device (3) is communicated with the tritium pipeline (1).
5. The tritium production module system of claim 4, wherein: the fluid accelerating device (3) is of a structure with a variable sectional area, the fluid accelerating device (3) comprises a contraction section, or a contraction section, a narrow throat section and an expansion section which are sequentially connected along the flowing direction, 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.
6. The tritium production module system of claim 5, wherein: the tritium production module system further comprises cladding (4) and tritium production layer groups, wherein the cladding (4) are arranged at intervals along the radial direction of the reactor, the tritium production layer groups are positioned between the cladding (4), the tritium production layer groups comprise tritium proliferation layers (6) and/or tritium proliferation multiplication layers (7), and the tritium pipeline (1) is at least partially positioned in the tritium production layer groups.
7. The tritium production module system of claim 6, wherein: the tritium-producing layer group comprises a neutron multiplication layer (5) and a tritium multiplication layer (6) which are arranged along the radial direction of the reactor, the tritium multiplication layer (6) is positioned on the outer side of the neutron multiplication layer (5), and the tritium pipeline (1) is at least partially positioned in the tritium multiplication layer (6).
8. The tritium production module system of claim 7, wherein: the tritium-producing module system further comprises a partition board (9), wherein the partition board (9) is positioned between layers of different types in the tritium-producing layer group; the tritium-producing module system further comprises a tritium-proof permeation layer, the tritium-proof permeation layer is adjacent to the cladding (4) and adopts a coating or low-permeation structure, the tritium-proof 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 。
9. The tritium production module system of claim 8, wherein: the tritium-producing module system further comprises a reflecting layer or a moderating layer (10), wherein the material of the reflecting layer or the moderating layer (10) 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.
10. The tritium production module system of claim 9, wherein: the tritium producing module system further comprises a radiation product producing layer (11), wherein the material of the radiation product producing layer (11) 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, said spacers (9) being arranged on both sides of the production layer (11) of the irradiated product.
11. The tritium production module system of claim 10, wherein: the tritium production module system comprises an cladding (4), a tritium prevention permeation layer, a neutron multiplication layer (5), a partition plate (9), a tritium multiplication layer (6), the partition plate (9), a radiation product production layer (11), the partition plate (9), a reflection layer or a moderation layer (10), the tritium prevention permeation layer and the cladding (4) which are sequentially arranged along the radial direction of the reactor from inside to outside.
12. The tritium production module system of claim 7, wherein: the tritium-producing layer group comprises a first circulating structure, wherein the neutron multiplication layer (5) and the tritium multiplication layer (6) which are arranged along the radial direction of the reactor circulate for a plurality of times in the first circulating structure;
or the tritium-producing layer group comprises a second circulation structure, and in the second circulation structure, any permutation and combination of the neutron multiplication layer (5), the tritium multiplication layer (6) and the tritium multiplication layer (7) which are arranged along the radial direction of the reactor is circulated for a plurality of times.
13. The tritium production module system of claim 6, wherein: the tritium-producing layer group comprises a tritium multiplication layer (7), the tritium multiplication layer (7) comprises a neutron multiplication part (12) and a cylindrical tritium multiplication part (13), a plurality of tritium multiplication parts (13) are uniformly arranged in the neutron multiplication part (12), and the volume ratio of the neutron multiplication part (12) to the tritium multiplication part (13) is 2:1 to 8: within the range of 1, the tritium pipelines (1) are arranged in an array in the tritium proliferation part (13).
14. The tritium production module system of any one of claims 6-13, wherein: the tritium producing module system is in a circular column shape and completely surrounds the periphery of a reactor core (14) of the reactor in the circumferential direction, is formed by splicing a plurality of tritium producing submodules in the circumferential direction, and has the quantity of 4-24 tritium producing submodules.
15. The tritium production module system of any one of claims 7-12, wherein: the neutron multiplication layer (5) comprises neutron multiplication material balls, wherein neutron multiplication materials are arranged in the neutron multiplication material balls, and the neutron multiplication materials comprise beryllium and beryllium-containing compounds;
the tritium proliferation layer (6) comprises a tritium proliferation material ball, wherein the tritium proliferation material ball is provided with the tritium proliferation material, and the tritium proliferation material comprises one or a mixture of more 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.
16. The tritium production module system of claim 15, wherein: the tritium multiplication layer (7) comprises the neutron multiplication material balls and the tritium multiplication material balls;
or the tritium multiplication layer (7) comprises a tritium multiplication material ball, the tritium multiplication material is arranged on the spherical center part of the tritium multiplication material ball, and the neutron multiplication material is arranged on the spherical shell part of the tritium multiplication material ball.
17. The tritium production module system of claim 14, wherein: the enrichment degree of Li-6 in the tritium proliferation material is 7.5% -90%, the enrichment degree of Li-7 is 10% -92.5%, and the total enrichment degree of Li-6 and Li-7 is 100%; the tritium breeder material having an enrichment of 50% -92.5% of the Li-7 is disposed proximate to the core (14) and the tritium breeder material having an enrichment of 50% -90% of the Li-6 is disposed distal to the core (14).
18. The tritium production module system of any one of claims 7-12, wherein: neutron multiplication layer (5) tritium multiplication layer (6) with tritium multiplication layer (7) all include the tritium group air inlet that produces, tritium group air inlet is provided with bearing structure and first filter screen (8), is used for preventing the material in the tritium group leaks outward.
19. The tritium production module system of claim 18, wherein: a second filter screen or a filter membrane is arranged on the inner side or the outer side of the pipe wall of the tritium pipe (1) so as to prevent materials or dust in the tritium-producing layer group from entering the tritium pipe (1).
20. A gas cooled reactor, characterized by: tritium production module system comprising a tritium production module system according to any one of claims 1-19, which is arranged at the periphery of a core (14) of the gas cooled reactor (25), which tritium production module system reacts with neutrons of the core (14) to produce tritium elements.
21. A gas cooled reactor as in claim 20, wherein: the gas cooled reactor (25) comprises a reactor core (14), a nuclear fuel seal isolation layer (16) and a reactor pressure vessel (17) which are arranged along the radial direction of the reactor core from inside to outside, and the tritium production module system is positioned between the nuclear fuel seal isolation layer (16) and the reactor pressure vessel (17).
22. A gas cooled reactor as set forth in claim 21, wherein: the nuclear fuel containment barrier (16) includes a metal container or shroud and also includes a stationary support member.
23. A gas cooled reactor as set forth in claim 21, wherein: the gas cooled reactor (25) further comprises a neutron modifying layer comprising a first neutron modifying layer (15), a second neutron modifying layer and a third neutron modifying layer, the neutron modifying layer comprising a coolant flow channel and/or a neutron multiplying layer and/or a reflecting layer and/or a moderating layer.
24. A gas cooled reactor as in claim 23, wherein: the second neutron regulating layer is arranged between the nuclear fuel sealing isolation layer (16) and the tritium producing module system.
25. A gas cooled reactor as in claim 23, wherein: the third neutron regulation layer is arranged between the reactor pressure vessel (17) and the tritium production module system.
26. A gas cooled reactor as in claim 23, wherein: the first neutron regulating layer (15) is arranged between the reactor core (14) and the nuclear fuel seal isolation layer (16).
27. A tritium system, characterized by: a tritium production module system comprising any one of claims 1-19, further comprising a tritium fuel supply system (18), the tritium production module system being connected to the tritium fuel supply system (18), a reactor coolant and a tritium-containing medium in the tritium production module system being fed into the tritium fuel supply system (18) to obtain tritium and/or helium-3 fuel, and the tritium fuel and/or the helium-3 fuel being fed to a fusion reactor (26).
28. The tritium system of claim 27, wherein: the tritium fuel supply system (18) comprises a tritium collection system (19), a tritium treatment storage system (20) and a tritium supplementing system (21) which are sequentially connected, wherein the tritium collection system (19) is connected with the tritium production module system, and the tritium supplementing system (21) is connected with the fusion reactor (26).
29. The tritium system of claim 28, wherein: the tritium treatment storage system (20) includes: the device comprises a tritium extraction system (22), a tritium purification and separation system (23), a tritium storage system (24) and a tritium monitoring system, wherein the tritium monitoring system is respectively associated with the tritium extraction system (22), the tritium purification and separation system (23) and the tritium storage system (24) and monitors equipment and facilities of each system.
30. The tritium system of claim 28, wherein: the tritium collection system (19) comprises: a tritium purification system, a tritium diversion system, a gas cooling and tritium conversion/catalysis system.
31. The tritium system of claim 28, wherein: the tritium replenishment system (21) comprises: a feed pretreatment system and a tritium injection system.
CN202310827029.6A 2023-07-06 2023-07-06 Tritium production module system, gas cooled reactor and tritium system Pending CN116759114A (en)

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