CN114068050B - Nuclear reactor plant based on solid coolant - Google Patents
Nuclear reactor plant based on solid coolant Download PDFInfo
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- CN114068050B CN114068050B CN202111543676.1A CN202111543676A CN114068050B CN 114068050 B CN114068050 B CN 114068050B CN 202111543676 A CN202111543676 A CN 202111543676A CN 114068050 B CN114068050 B CN 114068050B
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- 239000007787 solid Substances 0.000 title claims abstract description 83
- 239000002826 coolant Substances 0.000 title claims abstract description 81
- 239000006096 absorbing agent Substances 0.000 claims abstract description 55
- 238000011049 filling Methods 0.000 claims abstract description 23
- 238000000926 separation method Methods 0.000 claims abstract description 20
- 238000002955 isolation Methods 0.000 claims abstract description 15
- 238000006243 chemical reaction Methods 0.000 claims abstract description 10
- 230000004992 fission Effects 0.000 claims abstract description 8
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 6
- 239000000843 powder Substances 0.000 claims description 29
- 239000000446 fuel Substances 0.000 claims description 13
- 238000002347 injection Methods 0.000 claims description 12
- 239000007924 injection Substances 0.000 claims description 12
- 239000002245 particle Substances 0.000 claims description 8
- 238000010521 absorption reaction Methods 0.000 claims description 7
- 229910010271 silicon carbide Inorganic materials 0.000 claims description 7
- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 claims description 7
- 230000000712 assembly Effects 0.000 claims description 3
- 238000000429 assembly Methods 0.000 claims description 3
- 230000003139 buffering effect Effects 0.000 claims description 3
- 238000000605 extraction Methods 0.000 claims description 3
- 238000001914 filtration Methods 0.000 claims description 3
- 230000002285 radioactive effect Effects 0.000 claims description 2
- 230000007797 corrosion Effects 0.000 abstract description 7
- 238000005260 corrosion Methods 0.000 abstract description 7
- 239000000941 radioactive substance Substances 0.000 abstract description 5
- 238000011084 recovery Methods 0.000 abstract description 3
- 239000007789 gas Substances 0.000 description 16
- 230000032258 transport Effects 0.000 description 13
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 13
- 150000003839 salts Chemical class 0.000 description 8
- 239000007788 liquid Substances 0.000 description 7
- 230000000694 effects Effects 0.000 description 6
- 229910001338 liquidmetal Inorganic materials 0.000 description 6
- 238000000034 method Methods 0.000 description 6
- 238000001816 cooling Methods 0.000 description 5
- 239000002574 poison Substances 0.000 description 5
- 231100000614 poison Toxicity 0.000 description 5
- CURLTUGMZLYLDI-UHFFFAOYSA-N Carbon dioxide Chemical compound O=C=O CURLTUGMZLYLDI-UHFFFAOYSA-N 0.000 description 4
- 230000009471 action Effects 0.000 description 4
- ZOXJGFHDIHLPTG-UHFFFAOYSA-N Boron Chemical compound [B] ZOXJGFHDIHLPTG-UHFFFAOYSA-N 0.000 description 3
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 description 3
- 229910052796 boron Inorganic materials 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 239000002901 radioactive waste Substances 0.000 description 3
- 239000000243 solution Substances 0.000 description 3
- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 0.000 description 2
- 238000005299 abrasion Methods 0.000 description 2
- 229910052793 cadmium Inorganic materials 0.000 description 2
- BDOSMKKIYDKNTQ-UHFFFAOYSA-N cadmium atom Chemical compound [Cd] BDOSMKKIYDKNTQ-UHFFFAOYSA-N 0.000 description 2
- 239000001569 carbon dioxide Substances 0.000 description 2
- 229910002092 carbon dioxide Inorganic materials 0.000 description 2
- 239000000919 ceramic Substances 0.000 description 2
- 239000004020 conductor Substances 0.000 description 2
- 239000000945 filler Substances 0.000 description 2
- 229910002804 graphite Inorganic materials 0.000 description 2
- 239000010439 graphite Substances 0.000 description 2
- 229910052735 hafnium Inorganic materials 0.000 description 2
- VBJZVLUMGGDVMO-UHFFFAOYSA-N hafnium atom Chemical compound [Hf] VBJZVLUMGGDVMO-UHFFFAOYSA-N 0.000 description 2
- 239000000463 material Substances 0.000 description 2
- 239000000203 mixture Substances 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 239000012798 spherical particle Substances 0.000 description 2
- 229910052580 B4C Inorganic materials 0.000 description 1
- 229910000712 Boron steel Inorganic materials 0.000 description 1
- XUIMIQQOPSSXEZ-UHFFFAOYSA-N Silicon Chemical group [Si] XUIMIQQOPSSXEZ-UHFFFAOYSA-N 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 230000009286 beneficial effect Effects 0.000 description 1
- 238000009835 boiling Methods 0.000 description 1
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 1
- 239000004327 boric acid Substances 0.000 description 1
- INAHAJYZKVIDIZ-UHFFFAOYSA-N boron carbide Chemical compound B12B3B4C32B41 INAHAJYZKVIDIZ-UHFFFAOYSA-N 0.000 description 1
- 238000005253 cladding Methods 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000007596 consolidation process Methods 0.000 description 1
- 238000010276 construction Methods 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000011161 development Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 230000005484 gravity Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 239000001307 helium Substances 0.000 description 1
- 229910052734 helium Inorganic materials 0.000 description 1
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 238000003780 insertion Methods 0.000 description 1
- 230000037431 insertion Effects 0.000 description 1
- 238000011068 loading method Methods 0.000 description 1
- 238000002844 melting Methods 0.000 description 1
- 230000008018 melting Effects 0.000 description 1
- 229910052751 metal Inorganic materials 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000009428 plumbing Methods 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 238000012216 screening Methods 0.000 description 1
- 238000007711 solidification Methods 0.000 description 1
- 230000008023 solidification Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
- G21C15/28—Selection of specific coolants ; Additions to the reactor coolants, e.g. against moderator corrosion
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C7/00—Control of nuclear reaction
- G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
-
- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
The application discloses a nuclear reactor device based on solid coolant, comprising: the device comprises a reactor core, a heat exchange unit, a first conveying assembly, a second conveying assembly, a first distributing assembly, a second distributing assembly, a first buffer isolation assembly, a separation control unit, a first filling assembly, a second filling assembly, a first cavity and a second cavity; the core generates heat through a nuclear fuel fission reaction; the first filling assembly is used for filling neutron absorbers into the first cavity, and the first distribution assembly distributes different quantities of neutron absorbers into the second distribution assembly from the first cavity; the second distribution assembly distributes the solid coolant and the neutron absorber into a cavity where the reactor core is located; the second filling assembly is used for filling the solid coolant; the solid coolant and the neutron absorber sequentially pass through the cavity where the reactor core is located and the cavity where the heat exchange unit is located. The technical scheme of the application relieves the technical problems of corrosion of the coolant to the nuclear reactor device and recovery of radioactive substances.
Description
Technical Field
The present application relates to the field of atomic energy technology, and more particularly to nuclear reactor devices based on solid coolant.
Background
A nuclear reactor, also known as an atomic energy reactor, is a device that can sustain a controllable, self-sustaining, chain-type nuclear fission reaction to achieve nuclear energy utilization. In the existing reactors, there are classified into a water cooled reactor, a gas cooled reactor, and a liquid metal cooled reactor, and a liquid molten salt cooled reactor according to coolant materials.
The water-cooled reactor is divided into a light water reactor and a heavy water reactor, wherein the light water reactor is a reactor which takes water and steam-water mixture as a coolant and a moderator, and is a mode for utilizing nuclear energy smoothly. The mode of loading nuclear fission heat energy into the light water reactor can be divided into a pressurized water reactor and a boiling water reactor, and is two reactor types adopted by most nuclear power plants internationally. The water cooling mode is adopted, the reactor shell is resistant to the maximum pressure, the working pressure can be greatly improved along with the improvement of the working temperature, and the water can react with the metal wrapping the fuel at the extremely high temperature to cause risks. Water also presents problems of corrosiveness to the reactor shell and plumbing, as well as recovery of radioactive materials in the water coolant.
A gas cooled reactor refers to a reactor cooled with graphite, carbon dioxide or helium. Graphite gas cooled stacks cooled with carbon dioxide have been the leading stage in the development of nuclear power plants. However, the air cooled reactor is technically complex and high in cost, and is difficult to popularize and apply.
The liquid metal cooling pile and the liquid molten salt cooling pile adopt liquid metal or liquid molten salt as a coolant, the reactor core is pressureless, the reactor core has higher density and higher cooling efficiency than water, and high power density can be realized. However, there is a risk of leakage ignition of the liquid metal, problems of corrosion and activation of the liquid metal and the liquid molten salt, which cause products, and the liquid metal and the liquid molten salt solidify at low temperature, and additional heating and temperature maintaining systems must be designed.
In view of this, the present application proposes a nuclear reactor plant based on a solid coolant, in order to alleviate the problems of the prior art.
Disclosure of Invention
According to some embodiments, the present application provides a solid coolant based nuclear reactor device comprising: the device comprises a reactor core, a heat exchange unit, a first conveying assembly, a second conveying assembly, a first distributing assembly, a second distributing assembly, a first buffer isolation assembly, a separation control unit, a first filling assembly, a second filling assembly, a first cavity and a second cavity; the reactor core comprises a fuel assembly and a control rod, wherein the fuel assembly generates heat through nuclear fuel fission reaction, and the control rod controls the power of the reactor core through absorbing neutrons; the first filling assembly is used for filling neutron absorbers into the first cavity, and the first distribution assembly distributes different quantities of neutron absorbers into the second distribution assembly from the first cavity according to the working condition of the nuclear reactor; the second distribution assembly distributes solid coolant and neutron absorber in a cavity where the reactor core is located, wherein the solid coolant is in a solid form, and the neutron absorber is solid particles containing neutron absorption elements; the second filling assembly is used for filling the solid coolant; the solid coolant and the neutron absorber sequentially pass through the cavity where the reactor core is located and the cavity where the heat exchange unit is located; after the solid coolant absorbs heat of the reactor core, the solid coolant reaches a cavity where the heat exchange unit is positioned through the first buffer isolation assembly; the first buffer isolation component is used for isolating the cavity where the radioactive rays enter the heat exchange unit; the solid coolant exchanges heat with working medium in the heat exchange unit in the cavity where the heat exchange unit is located; the diameter or granularity of the neutron absorber is smaller than that of the solid coolant, and when the separation control unit is in a first state, the first conveying assembly conveys the neutron absorber and the solid coolant to the second distribution assembly; when the separation control unit is in the second state, the neutron absorber enters the second cavity, and the second conveying assembly conveys the neutron absorber to the first cavity.
Optionally, the solid coolant is spherical solid particles or powder.
Optionally, the solid coolant is silicon carbide.
Optionally, the nuclear reactor device further comprises: the powder that wear and tear of solid coolant, neutron absorber produced passes through separation control unit and filter assembly and reaches the powder collection room, and filter assembly is used for filtering the powder, and the powder collection room is used for collecting the powder.
Optionally, the nuclear reactor device further comprises: and the second buffer isolation assembly is arranged below the heat exchange unit and is used for buffering the movement speed of the solid coolant and the neutron absorber flowing through the heat exchange unit.
Optionally, the nuclear reactor device further comprises: and a gas injection unit for controlling injection and extraction of gas from the gas injection unit into the nuclear reactor device.
The beneficial effects of the application are as follows: in the circulation loop of the nuclear reactor device, a solid coolant is arranged to replace the traditional liquid or gaseous coolant, so that the pressureless or low-pressure reactor is realized, the corrosion of the coolant to the nuclear reactor device in the prior art is relieved, the rapid switching of modes such as high power, low power, shutdown and the like is realized, and the technical problems of simplicity and safety in radioactive substance recovery are realized. The solid coolant is adopted, so that the technical effects of no pressure, no corrosion, no cooling agent shutdown, no solidification, no leakage and no combustion of the reactor core in the nuclear reactor device are realized; in addition, the technical effects of quick shutdown and quick restarting are achieved through the addition and separation of the neutron absorber in the nuclear reactor device; the radioactive waste is solid, so that the characteristic that the radioactive waste is very easy to treat is brought, and the existing technical problem is relieved; meanwhile, since the solid heat conducting material generally has heavier atomic nuclei, the nuclear reactor device is supported to be designed into a fast neutron breeder reactor.
Drawings
In order to more clearly illustrate the embodiments of the present application or the technical solutions in the prior art, the drawings that are needed in the description of the embodiments or the prior art will be briefly described, and it is obvious that the drawings in the description below are some embodiments of the present application, and other drawings can be obtained according to the drawings without inventive effort for a person skilled in the art.
FIG. 1 is a schematic view of a solid coolant based nuclear reactor plant in accordance with an embodiment of the present application.
Reference numerals illustrate: 1-a core; 2-a heat exchange unit; 3-a first transport assembly; 4-a second transport assembly; 10-a first deployment assembly; 11-a second deployment assembly; 20-a first buffer isolation assembly; 30-a separation control unit; 50-a first filling assembly; 51-a second filling assembly; 90-a first cavity; 91-a second cavity; 70-a solid coolant; 80-neutron absorber; 40-a filter assembly; 60-a powder collection chamber; a second buffer isolation assembly 21; 100-a gas control unit; 101-gas injection assembly.
Detailed Description
For the purpose of making the objects, technical solutions and advantages of the embodiments of the present application more apparent, the technical solutions of the present application will be clearly and completely described below with reference to the accompanying drawings, wherein the described embodiments are some embodiments of the present application, but not all embodiments.
FIG. 1 is a schematic view of a solid coolant based nuclear reactor plant in accordance with an embodiment of the present application.
As shown in fig. 1, the nuclear reactor device includes: the reactor core 1, the heat exchange unit 2, the first transport assembly 3, the second transport assembly 4, the first placement assembly 10, the second placement assembly 11, the first buffer isolation assembly 20, the separation control unit 30, the first injection assembly 50, the second injection assembly 51, the first cavity 90, and the second cavity 91. In the vertical direction, the height of the core 1 is greater than the height of the heat exchange unit 2, and the solid coolant 70 flows to the heat exchange unit 2 after flowing through the core 1. The solid coolant 70 is in a solid state in the nuclear reactor device. Compared with the existing nuclear reactor device, the solid coolant can realize the technical effects of no pressure, no corrosion and easy throwing of the reactor core in the nuclear reactor device. Meanwhile, since the solid heat conducting material generally has heavier atomic nuclei, the nuclear reactor device is supported to be designed into a fast neutron breeder reactor.
The core 1 contains fuel assemblies that generate heat through nuclear fuel fission reactions, and control rods that control the power of the core 1 by absorbing neutrons. The fuel assembly is made up of several fuel elements. The fuel element is composed of a nuclear fuel and cladding, with fission reactions of the nuclear 235U、233U、239 Pu nuclei occurring within the fuel element, while optionally 238U、232 Th can absorb fast neutrons to regenerate the nuclear fuel. Illustratively, the fuel element may be in the shape of a rod or tube.
In an alternative embodiment, the fuel assembly is assembled from shaped fuel elements in a grid arrangement with various components. The fuel assemblies and control rods of the core 1 are inserted into the core 1 from the horizontal direction, and the solid coolant 70 flows in the vertical direction, so that a larger contact area of the solid coolant 70 with the core 1 is structurally ensured.
The first filling assembly 50 injects neutron absorber 80 into the first cavity 90, and the first deployment assembly 10 deploys a different amount of neutron absorber 80 from the first cavity 90 to the second deployment assembly 11 depending on the nuclear reactor operating conditions; the second distribution assembly 11 distributes the solid coolant 70 and the neutron absorber 80 in the cavity where the core 1 is located; the second filling assembly 51 is used to fill the solid coolant 70, and the neutron absorber 80 is solid particles containing neutron absorbing elements.
Illustratively, the solid coolant 70 and neutron absorber 80 pass through the cavity in which the core 1 is located and the cavity in which the heat exchange unit 2 is located sequentially under the effect of gravity.
Depending on the nuclear reactor operating conditions, the first filler assembly 50 transports a different amount of neutron absorber 80 to the first deployment assembly 10. The amount of neutron absorber 80 may affect the output power of the nuclear reactor. The core 1 can be realized by controlling the amount of neutron absorber 80 in addition to conventional control rods in terms of neutron absorption. If the number of neutron absorbers 80 is large, neutrons are absorbed in large quantities during the chain reaction of the core 1, the power produced by the core 1 is reduced even below the threshold and is shut down.
Illustratively, the neutron absorber 80 may be a composition comprising: ceramic inclusions of boron, cadmium or hafnium. Boron not only has a high neutron absorption cross section, but also has a wider neutron absorption energy range, and generally boron carbide or boron steel is used as a control material; the thermal neutron absorption section of cadmium is higher than that of boron; hafnium has a high absorption cross section for thermal neutrons and epithermal neutrons, and is a long-life neutron absorber.
It should be noted that the first filling component 50 does not transport the working fluid 80 to the first deployment component 10, and the nuclear reactor is at its maximum reaction strength.
In one embodiment, the neutron absorber 80 contains a neutron poison and the first filler assembly 50 transports the neutron poison to the first deployment assembly 10. The first deployment assembly 10 releases the neutron poison into the cavity in which the core 1 is located. After the neutron poison reaches the reactor core 1, the technical effect of nuclear reactor shutdown is achieved. Illustratively, the neutron poison may be boric acid.
After absorbing the heat of the core 1, the solid coolant 70 passes through the first buffer isolation assembly 20 and reaches the cavity where the heat exchange unit 2 is located; the first buffer isolation component 20 is used for isolating radioactive substances from the cavity where the radioactive substances enter the heat exchange unit 2; the solid coolant 70 exchanges heat with the working medium in the heat exchange unit 2 in the cavity in which the heat exchange unit 2 is located.
Illustratively, the separation control unit 30 performs separation control according to the diameters of the neutron absorber 80 and the solid coolant 70. Illustratively, the neutron absorber 80 has a smaller diameter than the solid coolant 70. When the separation control unit 30 is in the first state, the first transport assembly 3 transports the neutron absorber 80 and the solid coolant 70 to the second deployment assembly 11; when the separation control unit 30 is in the second state, the neutron absorber 80 enters the second cavity 91, and the second transporting assembly 4 transports the neutron absorber 80 to the first cavity 90.
In the nuclear reactor, the solid coolant 70 is circulated by:
a) The solid coolant 70 absorbs heat at the core 1;
b) The solid coolant 70 releases heat at the heat exchange unit 2;
c) The solid coolant 70 is transported by the first transport assembly 3 and distributed to the core 1 by the second distribution assembly 11 to absorb heat.
The circulation of neutron absorber 80 is divided into two cases, one of which is identical to solid coolant 70; alternatively, after the neutron absorber 80 enters the second cavity 91, the second transporting assembly 4 transports the neutron absorber 80 to the first cavity 90, and the first distributing assembly 10 may transport the neutron absorber 80 to the second distributing assembly 11, or may store the neutron absorber 80 in the first cavity 90. By the addition and separation of neutron absorber 80 within a nuclear reactor plant, the technical effects of controlling reactor power, shutdown, and restart may be achieved.
It should be noted that, the present embodiment can realize a pressureless reactor core, realize lower construction and operation costs of the reactor, avoid the problem of molten salt consolidation caused by corrosion of molten salt of the molten salt reactor core to a pipeline and shutdown cooling, reduce the complexity of the reactor, and realize miniaturization of the reactor. According to the embodiment, through the insertion of the traditional reactor core control rod and the input and screening out of the solid neutron absorber, flexible reactor core power control can be realized, and the quick start and stop of the reactor core can be realized; according to the embodiment, the solid coolant is distributed, the coolant is controlled to be thrown, and the control of neutron deceleration can be realized, so that a fast reactor operation mode is realized, and 238U、233 Th can be utilized; the embodiment simplifies the collection and treatment of radioactive waste by using solid coolant for the core, as compared to liquid and gas coolant, thereby reducing operating costs.
In one embodiment, the solid coolant 70 is spherical solid particles or powder. Spherical solid particles or powder, facilitating the flow of the solid coolant 70 within the nuclear reactor plant. The solid coolant 70 may be, for example, spherical particles or powder that are smooth, high temperature resistant, ultra-hard, and wear resistant, or spherical particles or powder with a smooth, high temperature resistant, ultra-hard, and wear resistant skin.
In one embodiment, the solid coolant 70 is silicon carbide. Silicon carbide is used as a coolant and is also a moderator for slowing down the neutron movement speed, and because the carbon core and the silicon core are heavier, the fast neutron value-added reaction can be realized through reasonable design. In addition, silicon carbide has the characteristics of corrosion resistance, high strength, high heat capacity at working temperature and good heat conduction performance, so that the silicon carbide is suitable for being used as a coolant. The silicon carbide has a melting point of 2700 ℃ and high temperature resistance, and can absorb heat of the reactor core 1 at high temperature.
In another alternative embodiment, solid coolant 70 is ceramic particles.
In one embodiment, the nuclear reactor device further comprises: the powder generated by abrasion of the solid coolant 70 passes through the separation control unit 30 and the filter assembly 40 to the powder collection chamber 60, the filter assembly 40 is used for filtering the powder, and the powder collection chamber 60 is used for collecting the powder. Illustratively, since the powder is much smaller in size than the solid coolant 70 and neutron absorber 80, the powder may pass through the separation control unit 30 whether the separation control unit 30 is in the first state or the second state. The powder may pass through the filter assembly 40, but the neutron absorber 80 cannot pass through the filter assembly 40. The powder produced by abrasion of the solid coolant 70 contains radioactive substances produced by fission reaction of the nuclear reactor, and thus the powder is recovered and processed by the powder collecting chamber 60.
In one embodiment, the nuclear reactor device further comprises: the second buffer isolation assembly 21 is disposed below the heat exchange unit 2, and is used for buffering the movement speed of the solid coolant 70 and the neutron absorber 80 flowing through the heat exchange unit 2.
In one embodiment, the nuclear reactor device further comprises: the gas control unit 100 and the gas injection assembly 101, the gas control unit 100 is used for controlling the injection of gas and the extraction of gas from the gas injection assembly 101 into the nuclear reactor device so as to regulate and control the gas in the reactor and further influence the action on the internal working condition.
Portions are not described in detail herein in terms of what is known in the art. It should be noted that in this document relational terms such as first and second, and the like are used solely to distinguish one entity or action from another entity or action without necessarily requiring or implying any actual such relationship or order between such entities or actions. Moreover, the terms "comprises," "comprising," or any other variation thereof, are intended to cover a non-exclusive inclusion, such that a process, method, article, or apparatus that comprises a list of elements does not include only those elements but may include other elements not expressly listed or inherent to such process, method, article, or apparatus. Without further limitation, an element defined by the phrase "comprising one … …" does not exclude the presence of other like elements in a process, method, article, or apparatus that comprises the element.
Finally, it should be noted that: it is apparent that the above examples are only illustrative of the present application and are not limiting of the embodiments. Other variations or modifications of the above teachings will be apparent to those of ordinary skill in the art. It is not necessary here nor is it exhaustive of all embodiments. And obvious variations or modifications thereof are contemplated as falling within the scope of the present application.
Claims (6)
1. A solid coolant based nuclear reactor plant, comprising: the device comprises a reactor core (1), a heat exchange unit (2), a first conveying assembly (3), a second conveying assembly (4), a first distributing assembly (10), a second distributing assembly (11), a first buffer isolation assembly (20), a separation control unit (30), a first filling assembly (50), a second filling assembly (51), a first cavity (90) and a second cavity (91);
The core (1) comprises fuel assemblies that generate heat through a nuclear fuel fission reaction, and control rods that control the power of the core (1) by absorbing neutrons;
The first filling assembly (50) is used for filling neutron absorbers (80) into the first cavity (90), and the first distribution assembly (10) distributes different quantities of the neutron absorbers (80) into the second distribution assembly (11) from the first cavity (90) according to the working condition of the nuclear reactor;
The second distribution assembly (11) distributes solid coolant (70) and neutron absorber (80) in a cavity where the reactor core (1) is located, the solid coolant (70) is in a solid form, and the neutron absorber (80) is solid particles containing neutron absorption elements;
-said second filling assembly (51) for filling a solid coolant (70);
The solid coolant (70) and the neutron absorber (80) sequentially pass through a cavity where the reactor core (1) is located and a cavity where the heat exchange unit (2) is located;
After the solid coolant (70) absorbs heat of the reactor core (1), the heat reaches a cavity where the heat exchange unit (2) is located through the first buffer isolation assembly (20); the first buffer isolation component (20) is used for isolating the cavity where the radioactive rays enter the heat exchange unit (2); the solid coolant (70) exchanges heat with working media in the heat exchange unit (2) in a cavity where the heat exchange unit (2) is located;
The neutron absorber (80) has a diameter or granularity smaller than that of the solid coolant (70), and the first conveying component (3) conveys the neutron absorber (80) and the solid coolant (70) to the second distributing component (11) when the separation control unit (30) is in a first state; when the separation control unit (30) is in the second state, the neutron absorber (80) enters the second cavity (91), and the second conveying assembly (4) conveys the neutron absorber (80) to the first cavity (90).
2. A nuclear reactor plant according to claim 1, characterized in that the solid coolant (70) is spherical solid particles or powder.
3. A nuclear reactor plant according to any one of claims 1 or 2, wherein the solid coolant (70) is silicon carbide.
4. The nuclear reactor plant as claimed in claim 1, further comprising: -a filter assembly (40) and-a powder collection chamber (60), the powder resulting from the wear of the solid coolant (70), neutron absorber (80) passing through the separation control unit (30) and the filter assembly (40) to the powder collection chamber (60), the filter assembly (40) being for filtering the powder, the powder collection chamber (60) being for collecting the powder.
5. The nuclear reactor plant as claimed in claim 1, further comprising: and the second buffer isolation assembly (21) is arranged below the heat exchange unit (2) and is used for buffering the movement speed of the solid coolant (70) and the neutron absorber (80) flowing through the heat exchange unit (2).
6. The nuclear reactor plant as claimed in claim 1, further comprising: and a gas control unit (100) and a gas injection unit (101), wherein the gas control unit (100) is used for controlling the injection of gas into the nuclear reactor device from the gas injection unit (101) and the extraction of gas.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111543676.1A CN114068050B (en) | 2021-12-17 | 2021-12-17 | Nuclear reactor plant based on solid coolant |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111543676.1A CN114068050B (en) | 2021-12-17 | 2021-12-17 | Nuclear reactor plant based on solid coolant |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN114068050A CN114068050A (en) | 2022-02-18 |
| CN114068050B true CN114068050B (en) | 2024-06-07 |
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Family Applications (1)
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Citations (5)
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|---|---|---|---|---|
| JP2002303691A (en) * | 2001-01-31 | 2002-10-18 | Central Res Inst Of Electric Power Ind | Solid-cooled reactor |
| NL2000078C2 (en) * | 2006-05-19 | 2007-11-20 | Gerrit Clemens Van Uitert | Nuclear reactor. |
| WO2016059364A1 (en) * | 2014-10-12 | 2016-04-21 | Ian Richard Scott | Reactivity control in a molten salt reactor |
| CN108780666A (en) * | 2015-12-15 | 2018-11-09 | 科利尔株式会社 | Radioactive nuclear reactor system can be eliminated |
| CN216596966U (en) * | 2021-12-17 | 2022-05-24 | 无锡博硕精睿科技有限公司 | Nuclear reactor device based on solid coolant |
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| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2002303691A (en) * | 2001-01-31 | 2002-10-18 | Central Res Inst Of Electric Power Ind | Solid-cooled reactor |
| NL2000078C2 (en) * | 2006-05-19 | 2007-11-20 | Gerrit Clemens Van Uitert | Nuclear reactor. |
| WO2016059364A1 (en) * | 2014-10-12 | 2016-04-21 | Ian Richard Scott | Reactivity control in a molten salt reactor |
| CN108780666A (en) * | 2015-12-15 | 2018-11-09 | 科利尔株式会社 | Radioactive nuclear reactor system can be eliminated |
| CN216596966U (en) * | 2021-12-17 | 2022-05-24 | 无锡博硕精睿科技有限公司 | Nuclear reactor device based on solid coolant |
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