CN114068050A - Nuclear reactor device based on solid coolant - Google Patents
Nuclear reactor device based on solid coolant Download PDFInfo
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- CN114068050A CN114068050A CN202111543676.1A CN202111543676A CN114068050A CN 114068050 A CN114068050 A CN 114068050A CN 202111543676 A CN202111543676 A CN 202111543676A CN 114068050 A CN114068050 A CN 114068050A
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- 239000002826 coolant Substances 0.000 title claims abstract description 80
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- 238000000926 separation method Methods 0.000 claims abstract description 18
- 238000009826 distribution Methods 0.000 claims abstract description 14
- 238000006243 chemical reaction Methods 0.000 claims abstract description 10
- 230000004992 fission Effects 0.000 claims abstract description 8
- 230000003139 buffering effect Effects 0.000 claims abstract description 7
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 7
- 239000000843 powder Substances 0.000 claims description 31
- 239000000446 fuel Substances 0.000 claims description 13
- 238000002955 isolation Methods 0.000 claims description 11
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- HBMJWWWQQXIZIP-UHFFFAOYSA-N silicon carbide Chemical compound [Si+]#[C-] HBMJWWWQQXIZIP-UHFFFAOYSA-N 0.000 claims description 6
- 238000005299 abrasion Methods 0.000 claims description 4
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- 239000000941 radioactive substance Substances 0.000 abstract description 4
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- XLYOFNOQVPJJNP-ZSJDYOACSA-N Heavy water Chemical compound [2H]O[2H] XLYOFNOQVPJJNP-ZSJDYOACSA-N 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
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Classifications
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- 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
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- 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 nuclear reactor device based on solid coolant includes: the reactor core, a heat exchange unit, a first transporting assembly, a second transporting assembly, a first distributing assembly, a second distributing assembly, a first buffering and isolating assembly, a separation control unit, a first filling assembly, a second filling assembly, a first cavity and a second cavity; the reactor core generates heat through nuclear fuel fission reaction; the first filling assembly injects neutron absorbers into the first cavity, and the first distribution assembly distributes different quantities of neutron absorbers in the second distribution assembly from the first cavity; the second distribution assembly distributes the solid coolant and the neutron absorber in the cavity where the reactor core is located; the second filling assembly is used for filling 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 nuclear power technology, and more particularly, to a solid coolant-based nuclear reactor plant.
Background
Nuclear reactors, also known as nuclear reactors, are devices that can sustain a controlled, self-sustaining, chain-type nuclear fission reaction to achieve nuclear energy utilization. In the existing reactor, the reactor is divided into a water cooled reactor, a gas cooled reactor, 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, the light water reactor is a reactor using water and steam-water mixture as coolant and moderator, and is a way of peacefully utilizing nuclear energy. The mode of carrying out nuclear fission thermal energy in the reactor by the light water reactor can be divided into a pressurized water reactor and a boiling water reactor, and the reactor is of two reactor types adopted by most international nuclear power stations. Adopt the water-cooled mode, pile the shell and endure very big pressure, and along with operating temperature's improvement, operating pressure also can very big improvement, and under high temperature, water can react with the metal of parcel fuel, causes the risk. Water also presents problems of corrosion of the reactor shell and piping, and recovery of radioactive materials from the water coolant.
The gas cooled reactor refers to a reactor which is cooled by graphite moderation and carbon dioxide or helium. The graphite gas cooled reactor cooled by carbon dioxide is in the leading position in the development of nuclear power stations in the early stage. However, the gas cooled reactor is technically complicated, has high manufacturing cost and is difficult to popularize and apply.
The liquid metal cooling reactor and the liquid molten salt cooling reactor adopt liquid metal or liquid molten salt as a coolant, have no pressure on a reactor core, have higher density and higher cooling efficiency than water, and can realize high power density. However, the liquid metal has the risk of leakage and fire, the problems of corrosion and activation of the liquid metal and the liquid molten salt which solidify at low temperatures, and additional warming and temperature maintaining systems must be designed.
In view of the above, the present application proposes a nuclear reactor device based on solid coolant to alleviate the prior art problems.
Disclosure of Invention
According to some embodiments, the present application provides a solid coolant based nuclear reactor apparatus comprising: the reactor core, a heat exchange unit, a first transporting assembly, a second transporting assembly, a first distributing assembly, a second distributing assembly, a first buffering and isolating 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 a nuclear fuel fission reaction, and the control rod controls the power of the reactor core through absorbing neutrons; the first filling assembly injects neutron absorbers into the first cavity, and the first distribution assembly distributes different quantities of neutron absorbers in 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 the cavity where the reactor core is located, the solid coolant is in a solid form, and the neutron absorber is solid particles containing neutron absorbing elements; the second filling assembly is used for filling 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 absorbing the heat of the reactor core, the solid coolant reaches the cavity where the heat exchange unit is located through the first buffer isolation assembly; the first buffer isolation assembly is used for isolating radioactive rays from entering the cavity where the heat exchange unit is located; the solid coolant is in the cavity where the heat exchange unit is located and exchanges heat with the working medium in the heat exchange unit; the diameter or the 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 a second state, the neutron absorber enters the second cavity, and the neutron absorber is transported to the first cavity by the second transporting assembly.
Optionally, the solid coolant is spherical solid particles or powder.
Optionally, the solid coolant is silicon carbide.
Optionally, the nuclear reactor apparatus further comprises: the device comprises a filtering assembly and a powder collecting chamber, wherein powder generated by abrasion of a solid coolant and a neutron absorber passes through a separation control unit and the filtering assembly and reaches the powder collecting chamber, the filtering assembly is used for filtering the powder, and the powder collecting chamber is used for collecting the powder.
Optionally, the nuclear reactor apparatus 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 apparatus further comprises: the gas control unit is used for controlling gas injection and gas extraction from the gas injection assembly into the nuclear reactor device.
The beneficial effect of this application is: in the circulation loop of the nuclear reactor device, a solid coolant is arranged to replace the traditional liquid or gaseous coolant, so that a non-pressure or low-pressure reactor is realized, the corrosion of the coolant to the nuclear reactor device in the prior art is relieved, the mode switching of high power, low power, shutdown and the like can be realized quickly, and the technical problems of simple radioactive substance recovery and safety are solved. The solid coolant is adopted, so that the technical effects of no pressure and no corrosion of a reactor core in the nuclear reactor device, no solidification of the coolant after shutdown, no leakage and no combustion are realized; in addition, the technical effects of fast shutdown and fast restart are achieved by adding and separating the neutron absorber in the nuclear reactor device; the radioactive wastes are all solid, so that the characteristic that the radioactive wastes are very easy to treat is brought, and the prior technical problem is solved; meanwhile, the solid heat conducting material generally has heavier atomic nucleus, so that the nuclear reactor device is supported to be designed into a fast neutron breeder reactor.
Drawings
In order to more clearly illustrate the detailed description of the present application or the technical solutions in the prior art, the drawings needed to be used in the detailed description of the present application or the prior art description will be briefly introduced below, and it is obvious that the drawings in the following description are some embodiments of the present application, and other drawings can be obtained by those skilled in the art without creative efforts.
FIG. 1 is a schematic diagram of a nuclear reactor plant based on a solid coolant according to an embodiment of the present application.
Description of reference numerals: 1-a reactor core; 2-a heat exchange unit; 3-a first transport assembly; 4-a second transport assembly; 10-a first laying assembly; 11-a second laying assembly; 20-a first buffer isolation assembly; 30-a separation control unit; 50-a first fill assembly; 51-a second fill assembly; 90-a first cavity; 91-a second cavity; 70-a solid coolant; 80-a neutron absorber; 40-a filter assembly; 60-a powder collection chamber; 21-a second buffer isolation component; 100-a gas control unit; 101-gas injection assembly.
Detailed Description
To make the objects, technical solutions and advantages of the embodiments of the present application clearer, the embodiments of the present application will be described in detail and completely with reference to the accompanying drawings, and the described embodiments are a part of the embodiments of the present application, but not all of the embodiments of the present application.
FIG. 1 is a schematic diagram of a nuclear reactor plant based on a solid coolant according to an embodiment of the present application.
As shown in fig. 1, the nuclear reactor apparatus includes: the reactor core comprises a reactor core 1, a heat exchange unit 2, a first transporting assembly 3, a second transporting assembly 4, a first arranging assembly 10, a second arranging assembly 11, a first buffering and isolating 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 height of the core 1 is greater than that of the heat exchange unit 2 in the vertical direction, and the solid coolant 70 flows toward the heat exchange unit 2 after flowing through the core 1. The solid coolant 70 is in a solid state in the reactor apparatus. Compared with the existing nuclear reactor device, the solid coolant can achieve the technical effects of no pressure, no corrosion and easy throwing of the reactor core in the nuclear reactor device. Meanwhile, the solid heat conducting material generally has heavier atomic nucleus, so that 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 a nuclear fuel fission reaction 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 nuclear fuel and cladding, the nuclear fuel235U、233U、239The fission reaction of the Pu nucleus takes place within the fuel element, optionally while238U、232Th can absorb fast neutrons to regenerate nuclear fuel. Illustratively, the fuel elements may be in the shape of rods or tubes.
In an alternative embodiment, the fuel assembly is assembled from shaped fuel elements by various components in a grid arrangement. 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, thereby structurally ensuring that the solid coolant 70 has a larger contact area with the core 1.
The first filling assembly 50 injects the neutron absorber 80 into the first cavity 90, and the first arranging assembly 10 arranges different amounts of the neutron absorber 80 in the second arranging assembly 11 from the first cavity 90 according to the working condition of the nuclear reactor; the second arrangement component 11 arranges the solid coolant 70 and the neutron absorber 80 in the cavity where the reactor core 1 is located; the second filling assembly 51 is used for filling the solid coolant 70, and the neutron absorber 80 is solid particles containing neutron-absorbing elements.
Illustratively, the solid coolant 70 and the neutron absorber 80 sequentially pass through the cavity in which the core 1 is located and the cavity in which the heat exchange unit 2 is located under the action of gravity.
The first fill assembly 50 delivers different amounts of neutron absorber 80 to the first placement assembly 10 depending on the nuclear reactor operating conditions. The amount of neutron absorber 80 may affect the output power of the nuclear reactor. The core 1 can be implemented by controlling the amount of the neutron absorber 80 in addition to the conventional control rods in terms of neutron absorption. If the amount of the neutron absorber 80 is large, the neutron is absorbed in a large amount during the chain reaction of the core 1, and the power generated by the core 1 is reduced even below the critical value, so that the reactor is shut down.
Illustratively, the neutron absorber 80 may be a neutron absorber containing: ceramic inclusions of boron, cadmium or hafnium. Boron has a high neutron absorption section and a wide energy range for absorbing neutrons, and generally takes boron carbide or boron steel as a control material; cadmium has a higher thermal neutron absorption cross-section than boron; hafnium has a high absorption cross section for both thermal neutrons and epithermal neutrons, and is a long-lived neutron absorber.
It should be noted that the first filling assembly 50 does not transport the working medium 80 to the first disposing assembly 10, and the nuclear reactor is at the maximum reaction intensity.
In one embodiment, the neutron absorber 80 contains neutron poison, the first filling assembly 50 transports the neutron poison to the first distribution assembly 10, and the first distribution assembly 10 releases the neutron poison to the cavity in which the core 1 is located. After the neutron poison reaches the reactor core 1, the technical effect of shutdown of the nuclear reactor 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 assembly 20 is used for isolating radioactive substances from entering the cavity where the heat exchange unit 2 is located; the solid coolant 70 exchanges heat with the working medium in the heat exchange unit 2 in the cavity where 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 transporting assembly 3 transports the neutron absorber 80 and the solid coolant 70 to the second placement 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 transport assembly 4 transports the neutron absorber 80 to the first cavity 90.
In the nuclear reactor, the circulation of the solid coolant 70 is as follows:
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 transporting assembly 3 and distributed to the reactor core 1 by the second distributing assembly 11 to absorb heat.
The circulation of the neutron absorber 80 is divided into two cases, one is the same as the solid coolant 70; the other is that after the neutron absorber 80 enters the second cavity 91, the second transport assembly 4 transports the neutron absorber 80 to the first cavity 90, and the first placement assembly 10 can transport the neutron absorber 80 to the second placement assembly 11 or store the neutron absorber 80 in the first cavity 90. It should be noted that the technical effects of controlling reactor power, shutdown and restart can be achieved by adding and separating the neutron absorber 80 into and from the nuclear reactor apparatus.
It should be noted that, in the embodiment, a pressureless reactor core can be realized, lower construction and operation costs of the reactor can be realized, corrosion of molten salt of the molten salt reactor core to a pipeline can be avoided, the problem of molten salt consolidation caused by shutdown cooling can be solved, the complexity of the reactor can be reduced, and the miniaturization of the reactor can be realized. In the embodiment, flexible reactor core power control can be realized and the reactor core can be quickly started and stopped by inserting the traditional reactor core control rods and inputting and screening out the solid neutron absorber; the true bookThe embodiment utilizes the distribution of the solid coolant to control the feeding of the coolant, and can realize the control of the deceleration of neutrons, thereby realizing the fast reactor operation mode and realizing the fast reactor operation mode238U、233Utilization of Th; this embodiment simplifies the collection and disposal of radioactive waste by using a solid coolant for the core, as compared to liquid and gaseous coolants, thereby reducing operating costs.
In one embodiment, the solid coolant 70 is a spherical solid particle or powder. The spherical solid particles or powder facilitate the flow of the solid coolant 70 within the nuclear reactor device. Illustratively, the solid coolant 70 may be 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 movement speed of neutrons, and because the carbon nucleus and the silicon nucleus 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 conductivity, and is suitable to be used as a coolant. The silicon carbide has a melting point of 2700 ℃, has high temperature resistance, and can absorb heat of the reactor core 1 at high temperature.
In another alternative embodiment, the solid coolant 70 is ceramic particles.
In one embodiment, the nuclear reactor apparatus further comprises: a filter assembly 40 and a powder collection chamber 60, powder generated by abrasion of the solid coolant 70 passes through the separation control unit 30 and the filter assembly 40 to reach 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 has a size much smaller than the solid coolant 70 and the neutron absorber 80, the powder can pass through the separation control unit 30 regardless of 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. Since the powder generated by abrasion of the solid coolant 70 contains radioactive substances generated by fission reaction of the nuclear reactor, the powder collection chamber 60 collects and disposes the powder.
In one embodiment, the nuclear reactor apparatus further comprises: 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.
In one embodiment, the nuclear reactor apparatus further comprises: the gas control unit 100 is used for controlling gas injection and gas extraction from the gas injection assembly 101 into the nuclear reactor device, so as to regulate and control gas in the reactor and further influence the effect on internal working conditions.
Details which are in part known in the art have not been set forth herein in detail. It is noted that, herein, relational terms such as first and second, and the like may be 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. Also, 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 an … …" does not exclude the presence of other identical elements in a process, method, article, or apparatus that comprises the element.
Finally, it should be noted that: it should be understood that the above examples are only for clearly illustrating the present application and are not intended to limit the embodiments. Other variations and modifications will be apparent to persons skilled in the art in light of the above description. And are neither required nor exhaustive of all embodiments. And obvious variations or modifications of this invention may be made without departing from the spirit or scope of the invention.
Claims (6)
1. A solid coolant based nuclear reactor apparatus, comprising: the reactor core comprises a reactor core (1), a heat exchange unit (2), a first transporting assembly (3), a second transporting assembly (4), a first arranging assembly (10), a second arranging assembly (11), a first buffering and isolating 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) contains fuel assemblies that generate heat by a nuclear fuel fission reaction and control rods that control the power of the core (1) by absorbing neutrons;
the first filling assembly (50) injects neutron absorbers (80) into the first cavity (90), and the first distribution assembly (10) distributes different amounts of the neutron absorbers (80) from the first cavity (90) to the second distribution assembly (11) according to the working conditions of the nuclear reactor;
the second distribution assembly (11) distributes a solid coolant (70) and a 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 absorbing elements;
the second filling assembly (51) is used for filling 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 absorbing the heat of the reactor core (1), the solid coolant (70) reaches a cavity where the heat exchange unit (2) is located through the first buffer isolation assembly (20); the first buffer isolation assembly (20) is used for isolating radioactive rays from entering a cavity where the heat exchange unit (2) is located; the solid coolant (70) is in a cavity where the heat exchange unit (2) is located, and exchanges heat with working media in the heat exchange unit (2);
the diameter or the granularity of the neutron absorber (80) is smaller than that of the solid coolant (70), when the separation control unit (30) is in a first state, the first conveying assembly (3) conveys the neutron absorber (80) and the solid coolant (70) to the second distribution 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 transportation assembly (4) transports the neutron absorber (80) to the first cavity (90).
2. A nuclear reactor plant according to claim 1, characterized in that said solid coolant (70) is a spherical solid particle or powder.
3. A nuclear reactor plant as claimed in either one of claims 1 and 2, characterized in that said solid coolant (70) is silicon carbide.
4. The nuclear reactor device according to claim 1, further comprising: the device comprises a filtering assembly (40) and a powder collecting chamber (60), wherein powder generated by abrasion of the solid coolant (70) and the neutron absorber (80) passes through a separation control unit (30) and the filtering assembly (40) and reaches the powder collecting chamber (60), the filtering assembly (40) is used for filtering the powder, and the powder collecting chamber (60) is used for collecting the powder.
5. The nuclear reactor device according to claim 1, further comprising: 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 device according to claim 1, further comprising: the gas injection device comprises a gas control unit (100) and a gas injection assembly (101), wherein the gas control unit (100) is used for controlling gas injection and gas extraction from the gas injection assembly (101) into the nuclear reactor device.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202111543676.1A CN114068050A (en) | 2021-12-17 | 2021-12-17 | Nuclear reactor device based on solid coolant |
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| Application Number | Priority Date | Filing Date | Title |
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| CN202111543676.1A CN114068050A (en) | 2021-12-17 | 2021-12-17 | Nuclear reactor device based on solid coolant |
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| CN114068050A true CN114068050A (en) | 2022-02-18 |
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| CN (1) | CN114068050A (en) |
Cited By (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115342595A (en) * | 2022-08-16 | 2022-11-15 | 兰州工业学院 | Cooling device with cooling medium capable of being changed |
| CN116313178A (en) * | 2023-04-13 | 2023-06-23 | 中国原子能科学研究院 | Reactor and reactivity control system thereof |
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| 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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| 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 |
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115342595A (en) * | 2022-08-16 | 2022-11-15 | 兰州工业学院 | Cooling device with cooling medium capable of being changed |
| CN115342595B (en) * | 2022-08-16 | 2023-03-21 | 兰州工业学院 | Cooling device with cooling medium capable of being changed |
| CN116313178A (en) * | 2023-04-13 | 2023-06-23 | 中国原子能科学研究院 | Reactor and reactivity control system thereof |
| CN116313178B (en) * | 2023-04-13 | 2024-03-22 | 中国原子能科学研究院 | Reactor and reactivity control system thereof |
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