CN113299409A - Small-size villaumite of spiral cross fuel element cools off high temperature reactor core - Google Patents
Small-size villaumite of spiral cross fuel element cools off high temperature reactor core Download PDFInfo
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- CN113299409A CN113299409A CN202110486428.1A CN202110486428A CN113299409A CN 113299409 A CN113299409 A CN 113299409A CN 202110486428 A CN202110486428 A CN 202110486428A CN 113299409 A CN113299409 A CN 113299409A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/02—Fuel elements
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/14—Means forming part of the element for inserting it into, or removing it from, the core; Means for coupling adjacent elements, e.g. to form a stringer
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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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/322—Means to influence the coolant flow through or around the bundles
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
- G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
- G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
- G21C3/326—Bundles of parallel pin-, rod-, or tube-shaped fuel elements comprising fuel elements of different composition; comprising, in addition to the fuel elements, other pin-, rod-, or tube-shaped elements, e.g. control rods, grid support rods, fertile rods, poison rods or dummy rods
- G21C3/328—Relative disposition of the elements in the bundle lattice
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/02—Details
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C5/00—Moderator or core structure; Selection of materials for use as moderator
- G21C5/14—Moderator or core structure; Selection of materials for use as moderator characterised by shape
- G21C5/16—Shape of its constituent parts
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- 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
- G21C7/08—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 by displacement of solid control elements, e.g. control rods
- G21C7/10—Construction of control elements
- G21C7/117—Clusters of control rods; Spider construction
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- 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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- Chemical Kinetics & Catalysis (AREA)
- Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
Abstract
The invention discloses a spiral cross fuel element small-sized villaumite cooling high-temperature reactor core, which comprises a core surrounding barrel, an upper chamber, an upper reflecting layer, a radial reflecting layer, a coolant bypass flow channel, a fuel assembly, a control rod assembly, a lower reflecting layer and a lower chamber, wherein the upper chamber, the upper reflecting layer, the radial reflecting layer, the coolant bypass flow channel, the fuel assembly, the control rod assembly, the lower reflecting layer and the lower chamber are positioned in the core surrounding barrel; the fuel assembly includes a fuel element, a coolant channel, and a graphite layer; the fuel element comprises a fuel area and a cladding; the control rod assembly comprises a control rod, a coolant channel and a graphite layer; the control rod comprises a control body, a gap and a guide tube. The invention adopts the spiral cross fuel element, increases the heat transfer area, enhances the turbidness of the reactor core coolant, and improves the heat exchange effect, thereby improving the power density of the reactor core. Meanwhile, the use of a positioning grid is avoided by means of mutual support among the spiral cross-shaped fuel elements, and the reactor core structure is simplified. The reactor core outputs heat through the molten salt heat exchanger and stores the heat in the energy storage pool, and the reactor core can be used for generating electricity and outputting high-temperature process heat, so that multipurpose utilization of the heat is realized.
Description
Technical Field
The invention relates to the technical field of reactor design, in particular to a small-sized villaumite-cooled high-temperature reactor core of a spiral cross fuel element.
Background
The fluoride salt cooled high-temperature reactor is a fourth-generation reactor which is provided by combining the advantages of a molten salt reactor, a high-temperature gas cooled reactor, a sodium cooled fast reactor and the like, takes fluoride salt as a coolant, takes coated particles as fuel, and has good safety, economy, sustainability and nuclear diffusion resistance.
The spiral cross fuel is a novel high-performance fuel, improves the thermal hydraulic performance of a fuel element by improving the geometric shape of the traditional nuclear fuel, can greatly improve the power density of a reactor core, and has wide application prospect in reactor design.
In the conceptual design scheme of the fluoride salt cooled high-temperature reactor proposed at home and abroad at present, fuel elements adopted by a reactor core comprise a cylinder type, a ring type, a plate type and a ball type, wherein the cylinder type and the ring type are not easy to install and position, flow-induced vibration is easy to generate in the operation process, the plate type fuel element has good mechanical property, but has high fuel peak temperature and short reactor core service life, and the fuel circulation scheme is more complicated due to the online refueling characteristic of the ball type fuel element, so that more researches are needed. Based on the problems of the existing villiaumite cooling high-temperature reactor fuel element, the invention discloses a novel fuel element which has small flow resistance and strong heat exchange capability and avoids the use of a spacer grid.
Disclosure of Invention
The invention aims to provide a spiral cross fuel element small-sized villaumite cooling high-temperature reactor core, which can strengthen reactor heat exchange and improve reactor performance.
In order to achieve the purpose, the invention adopts the following technical scheme:
a spiral cross fuel element small-sized villaumite-cooled high-temperature reactor core comprises a core shroud 1, an upper chamber 2 and a lower chamber 9 which are positioned in the core shroud 1, an upper reflecting layer 3 positioned between the upper chamber 2 and the lower chamber 9, a radial reflecting layer 4, a coolant bypass channel 5, a fuel assembly 6, a control rod assembly 7 and a lower reflecting layer 8; the fuel assembly 6 and the control rod assembly 7 are positioned among the radial reflecting layer 4, the upper reflecting layer 3 and the lower reflecting layer 8, the periphery of the fuel assembly 6 and the control rod assembly 7 comprises 36 coolant bypass channels 5, the upper part of each coolant bypass channel 5 penetrates through the upper reflecting layer 3, and the lower part of each coolant bypass channel 5 penetrates through the lower reflecting layer 8; the fuel assembly 6 comprises 19 fuel elements 12 which are arranged in a hexagonal shape, a coolant channel 14 among the fuel elements 12 and a graphite layer 13 which covers the fuel elements 12 and the coolant channel 14, wherein the fuel elements 12 are all in a spiral cross shape and are fixed by the support of the adjacent fuel elements; the fuel element 12 comprises a fuel area 10 and a cladding 11 covering the fuel area 10; the control rod assembly 7 comprises 7 control rods 18 which are arranged in a hexagonal shape, a coolant channel 14 among the control rods 18 and a graphite layer 13 which covers the control rods 18 and the coolant channel 14; the control rod 18 comprises a control body 17, a gap 16 around the control body 17 and a guide tube 15 around the gap 16.
The core comprises 78 fuel assemblies 6 and 13 control rod assemblies 7 in a hexagonal arrangement.
The fuel elements 12 are arranged in a hexagonal shape, and support and fixation are achieved by means of two contact points at each 30-degree torsion position of each fuel element 12, so that the number of the contact points is increased, and fixation is easier.
The fuel area 10 of the fuel element 12 is composed of a graphite matrix and TRISO coated fuel particles dispersed in the graphite matrix, and the fuel is UC0.5O1.5The uranium-235 enrichment was 19.75%, and the cladding 11 material of the fuel element 12 was graphite.
The control body 17 of the control rod 18 is filled with boron carbide, and the material of the guide tube 15 is graphite.
The coolant material in the coolant channel 14 is liquid molten salt FLiBe composed of LiF and BeF2Mixed at a molar ratio of 2:1, and driven by a main pump 21 to cool the core.
The coolant channels 14 of the fuel assembly 6 and the control rod assembly 7 are hexagonal in shape.
The upper reflecting layer 3, the radial reflecting layer 4 and the lower reflecting layer 8 are made of graphite.
The reactor core 20 is positioned in the pressure vessel 19, and the generated heat is driven by a molten salt pump 23 to output heat transfer working medium FLiNaK molten salt through a molten salt heat exchanger 22 and is collected in an energy storage pool 24 for multipurpose use of heat.
LiF in the FLiNaK molten salt: NaF: KF 46.5:11.5:42 mol%.
Compared with the prior art, the invention has the following advantages:
1. the reactor core of the small-sized villaumite-cooled high-temperature reactor adopts the spiral cross fuel element, compared with plate type, cylindrical type, annular type and spherical fuel elements of the existing villaumite reactor, the surface area and volume ratio of the fuel rod are increased, the spiral structure of the fuel rod impacts a coolant, the turbidness among sub-channels is enhanced, the heat exchange effect is greatly enhanced, and the power density is improved. The helical cross fuel element pocket surfaces also tend to accommodate swelling deformation, reducing stress.
2. The reactor core of the small-sized villiaumite-cooled high-temperature reactor adopts the spiral cross fuel elements which are arranged in a hexagon, and the fixation is realized by the support of the adjacent elements, so that the use of a positioning grid frame is avoided. Compared with the pressurized water reactor spiral cross fuel elements which are arranged in a rectangular mode, each fuel element has four contact points when the fuel elements are twisted for 90 degrees, the hexagonal arrangement of the fuel elements achieves supporting and fixing effects by means of two contact points when each fuel element is twisted for 30 degrees, so that the number of the contact points is increased, the fixation is easy, the hexagonal arrangement space utilization rate is high, and the reduction of the reactor core volume is facilitated.
3. The heat generated by the reactor core of the small-sized villiaumite-cooled high-temperature reactor is output by the fused salt pump driving the heat transfer working medium FLiNaK liquid fused salt through the fused salt heat exchanger and is collected in the energy storage pool, so that the power can be generated, the high-temperature process heat can be output, and the multipurpose use of the heat is realized.
4. According to the small-sized villaumite-cooled high-temperature reactor core, the control rods are arranged in the independent assemblies and are not in contact with fuel, so that the irradiation damage to the control rods is reduced.
Drawings
FIG. 1 is a longitudinal cross-sectional view of a core of a spiral cross fuel element small-sized villaumite-cooled high-temperature reactor.
FIG. 2 is a schematic cross-sectional view of a spiral cross fuel element small-scale villaumite-cooled high temperature reactor core of the present invention.
FIG. 3 is a schematic view of a fuel assembly.
FIG. 4 is a schematic view of a fuel element.
FIG. 5 is a schematic view of a control rod assembly.
FIG. 6 is a schematic diagram of core heat utilization.
In the above drawings: 1-a reactor core shroud; 2-an upper chamber; 3-an upper reflective layer; 4-a radially reflective layer; 5-coolant bypass flow channels; 6-a fuel assembly; 7-a control rod assembly; 8-a lower reflective layer; 9-a lower chamber; 10-fuel zone; 11-cladding; 12-a fuel element; 13-a graphite layer; 14-coolant channels; 15-a guide tube; 16-gap; 17-a control body; 18-a control rod; 19-a pressure vessel; 20-a core; 21-the main pump; 22-molten salt heat exchanger; 23-molten salt pump; 24-energy storage battery.
Detailed Description
The invention provides a spiral cross fuel element small-sized villaumite-cooled high-temperature reactor core, which is further described in detail with reference to the attached drawings.
Referring to fig. 1 and 2, an embodiment of a spiral cross fuel element small fluorine salt cooled high temperature stack of the present invention is shown.
The reactor comprises a reactor core shroud 1, an upper chamber 2 and a lower chamber 9 which are positioned in the reactor core shroud 1, an upper reflecting layer 3 positioned between the upper chamber 2 and the lower chamber 9, a radial reflecting layer 4, a coolant bypass flow channel 5, a fuel assembly 6, a control rod assembly 7 and a lower reflecting layer 8; the fuel assembly 6 and the control rod assembly 7 are positioned among the radial reflecting layer 4, the upper reflecting layer 3 and the lower reflecting layer 8, the periphery of the fuel assembly 6 and the control rod assembly 7 comprises 36 coolant bypass channels 5, the upper part of each coolant bypass channel 5 penetrates through the upper reflecting layer 3, and the lower part of each coolant bypass channel 5 penetrates through the lower reflecting layer 8; the core comprises 78 fuel assemblies 6 and 13 control rod assemblies 7 in a hexagonal arrangement.
As shown in fig. 3 and 4, the fuel assembly 6 comprises 19 fuel elements 12 arranged in a hexagonal shape, coolant channels 14 between the fuel elements 12, and graphite layers 13 covering the fuel elements 12 and the coolant channels 14, wherein the fuel elements 12 are all in a spiral cross shape and are fixed by the support of the adjacent fuel elements; the fuel element 12 includes a fuel region 10 and a cladding 11 encasing the fuel region 10.
As shown in fig. 5, the control rod assembly 7 includes 7 control rods 18 arranged in a hexagonal shape, coolant passages 14 between the control rods 18, and graphite layers 13 covering the control rods 18 and the coolant passages 14; the control rod 18 comprises a control body 17, a gap 16 at the periphery of the control body 17 and a guide pipe 15 at the periphery of the gap 16, wherein the gap 16 is used for reserving space for irradiation expansion, thermal expansion, gas generation and the like of the control body 17.
As shown in fig. 6, the reactor core 20 is located in the pressure vessel 19, and the generated heat is driven by the molten salt pump 23 to output the heat transfer working medium FLiNaK molten salt (LiF: NaF: KF ═ 46.5:11.5:42 mol%) through the molten salt heat exchanger 22 and is collected in the energy storage pool 24, so that the multipurpose use of the heat is realized.
As a preferred embodiment of the present invention, the fuel region 10 of the fuel element 12 is composed of a graphite matrix and TRISO-coated fuel particles dispersed in the graphite matrix, and can contain fission products more effectively, wherein the fuel is UC0.5O1.5The uranium-235 enrichment was 19.75%, and the cladding 11 material of the fuel element 12 was graphite.
In a preferred embodiment of the present invention, the control body 17 of the control rod 18 is filled with boron carbide, and the material of the guide tube 15 is graphite.
As a preferred embodiment of the invention, the coolant material in the coolant channels 14 is a liquid molten salt FLiBe, consisting of LiF and BeF2Mixed in a molar ratio of 2:1Driven by the main pump 21 to cool the core. FLiBe has higher specific heat capacity as the coolant, can make the reactor core volume littleer, and power density is bigger, and its heat conductivity is good, can effectively conduct the reactor core heat to have fine compatibility with graphite material.
As a preferred embodiment of the present invention, the coolant channels 14 of the fuel assemblies 6 and the control rod assemblies 7 are hexagonal in shape, so that the coolant distribution is more uniform.
In a preferred embodiment of the present invention, the upper reflective layer 3, the radial reflective layer 4 and the lower reflective layer 8 are made of graphite.
The working principle of the spiral cross fuel element small-sized villaumite cooling high-temperature reactor core is as follows:
when the spiral cross fuel element small-sized villiaumite cooling high-temperature reactor core operates, heat is generated by the fission of the TRISO coated particles in the fuel area 10, and is diffused to the outside of the fuel element 12 through the graphite matrix and the cladding 11, so as to be transferred to the coolant channel 14. Coolant salt enters the core from the lower chamber 9 and flows upward to conduct away fission heat and mix in the upper chamber 2. Fission-generated neutrons are moderated by the graphite matrix in the fuel zone 10 and the fuel assembly peripheral graphite layers 13, and the lifting or insertion of control rods 18 serves to control core reactivity.
The reactor core 20 is positioned in the pressure vessel 19, and the generated heat is driven by a molten salt pump 23 to output heat transfer working medium FLiNaK liquid molten salt (LiF: NaF: KF ═ 46.5:11.5:42 mol%) through a molten salt heat exchanger 22 and is collected in an energy storage pool 24. The stored heat can not only generate electricity, but also output high-temperature process heat, thereby realizing multipurpose use of the heat.
Claims (10)
1. A spiral cross-shaped fuel element small-sized villiaumite-cooled high-temperature reactor core is characterized by comprising a core shroud (1), an upper chamber (2) and a lower chamber (9) which are positioned in the core shroud (1), an upper reflecting layer (3) positioned between the upper chamber (2) and the lower chamber (9), a radial reflecting layer (4), a coolant bypass channel (5), a fuel assembly (6), a control rod assembly (7) and a lower reflecting layer (8); the fuel assembly (6) and the control rod assembly (7) are positioned among the radial reflecting layer (4), the upper reflecting layer (3) and the lower reflecting layer (8), the periphery of the fuel assembly (6) and the control rod assembly (7) comprises 36 coolant bypass flow channels (5), the upper parts of the coolant bypass flow channels (5) penetrate through the upper reflecting layer (3), and the lower parts of the coolant bypass flow channels penetrate through the lower reflecting layer (8); the fuel assembly (6) comprises 19 fuel elements (12) which are arranged in a hexagonal shape, a coolant channel (14) among the fuel elements (12) and a graphite layer (13) which covers the fuel elements (12) and the coolant channel (14), wherein the fuel elements (12) are all in a spiral cross shape and are fixed by the support of the adjacent fuel elements; the fuel element (12) comprises a fuel area (10) and a cladding (11) covering the fuel area (10); the control rod assembly (7) comprises 7 control rods (18) which are arranged in a hexagonal shape, a coolant channel (14) among the control rods (18) and a graphite layer (13) which covers the control rods (18) and the coolant channel (14); the control rod (18) comprises a control body (17), a gap (16) at the periphery of the control body (17) and a guide tube (15) at the periphery of the gap (16).
2. A spiral cross fuel element mini-fluoro-salt cooled high temperature reactor core as claimed in claim 1 wherein the core comprises 78 fuel assemblies (6) and 13 control rod assemblies (7) in a hexagonal array.
3. A spiral cruciform fuel element mini-villiaumite cooled high temperature reactor core as set forth in claim 1, wherein said fuel elements (12) are in a hexagonal array, and support and hold by means of two contact points per 30 degrees of twist of each fuel element (12) increases the number of contact points for easier holding.
4. The helical cruciform fuel element small-sized villiaumite-cooled high temperature reactor core as set forth in claim 1, wherein the fuel region (10) of the fuel element (12) is composed of a graphite matrix and TRISO-coated fuel particles dispersed in the graphite matrix, and the fuel is UC0.5O1.5The uranium-235 enrichment is 19.75%, and the cladding (11) material of the fuel element (12) is graphite.
5. A spiral cross fuel element small fluoride salt cooled high temperature reactor core as set forth in claim 1, characterized in that the control body (17) of the control rod (18) is filled with boron carbide and the material of the guide tube (15) is graphite.
6. A spiral cruciform fuel element mini-fluorate cooled high temperature reactor core as claimed in claim 1 wherein the coolant material in the coolant channels (14) is liquid molten salt FLiBe, consisting of LiF and BeF2Mixed in a molar ratio of 2:1, and driven by a main pump (21) to cool the core.
7. A spiral cruciform fuel element mini-fluoro-salt cooled high temperature reactor core as set forth in claim 1 wherein the coolant channels (14) of the fuel assemblies (6) and control rod assemblies (7) are hexagonal.
8. The helical cruciform fuel element small-sized villiaumite-cooled high temperature reactor core of claim 1, wherein the upper reflecting layer (3), the radial reflecting layer (4) and the lower reflecting layer (8) are made of graphite.
9. The spiral cross fuel element small-sized villiaumite cooled high-temperature reactor core as claimed in claim 1, characterized in that the core (20) is positioned in a pressure vessel (19), and the generated heat is output by a molten salt pump (23) to drive a heat transfer working medium FLiNaK molten salt through a molten salt heat exchanger (22) and is collected in an energy storage pool (24) for multipurpose use of the heat.
10. The spiral cruciform fuel element small fluoride salt cooled high temperature reactor core of claim 9, wherein the ratio of LiF: NaF: KF 46.5:11.5:42 mol%.
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Cited By (7)
| Publication number | Priority date | Publication date | Assignee | Title |
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| CN113793702A (en) * | 2021-08-25 | 2021-12-14 | 西安交通大学 | Intrinsic safety integrated small-sized villaumite cooling high-temperature reactor core |
| CN113793701A (en) * | 2021-08-25 | 2021-12-14 | 西安交通大学 | Spiral cross-shaped metal fuel element reactor core |
| CN113990535A (en) * | 2021-09-30 | 2022-01-28 | 中国科学院上海应用物理研究所 | Integrated molten salt reactor heat exchanger and passive residual heat removal system thereof |
| CN114005554A (en) * | 2021-10-22 | 2022-02-01 | 西安交通大学 | Fluoride salt cooling high-temperature reactor core based on spiral cross fuel element |
| CN114446496A (en) * | 2022-02-17 | 2022-05-06 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel element |
| WO2023077687A1 (en) * | 2021-11-05 | 2023-05-11 | 中广核研究院有限公司 | Fuel rod, fuel assembly, and reactor core |
| CN117174347A (en) * | 2023-07-26 | 2023-12-05 | 华能核能技术研究院有限公司 | High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof |
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Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN113793702A (en) * | 2021-08-25 | 2021-12-14 | 西安交通大学 | Intrinsic safety integrated small-sized villaumite cooling high-temperature reactor core |
| CN113793701A (en) * | 2021-08-25 | 2021-12-14 | 西安交通大学 | Spiral cross-shaped metal fuel element reactor core |
| CN113793701B (en) * | 2021-08-25 | 2022-12-09 | 西安交通大学 | Spiral cross-shaped metal fuel element reactor core |
| CN113990535A (en) * | 2021-09-30 | 2022-01-28 | 中国科学院上海应用物理研究所 | Integrated molten salt reactor heat exchanger and passive residual heat removal system thereof |
| CN113990535B (en) * | 2021-09-30 | 2023-07-28 | 中国科学院上海应用物理研究所 | Integrated molten salt reactor heat exchanger and passive waste heat discharging system thereof |
| CN114005554A (en) * | 2021-10-22 | 2022-02-01 | 西安交通大学 | Fluoride salt cooling high-temperature reactor core based on spiral cross fuel element |
| WO2023077687A1 (en) * | 2021-11-05 | 2023-05-11 | 中广核研究院有限公司 | Fuel rod, fuel assembly, and reactor core |
| CN114446496A (en) * | 2022-02-17 | 2022-05-06 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel element |
| CN114446496B (en) * | 2022-02-17 | 2024-04-23 | 中国核动力研究设计院 | Ultra-high flux reactor core based on annular fuel elements |
| CN117174347A (en) * | 2023-07-26 | 2023-12-05 | 华能核能技术研究院有限公司 | High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof |
| CN117174347B (en) * | 2023-07-26 | 2024-06-04 | 华能核能技术研究院有限公司 | High-temperature gas cooled reactor coolant bypass control method and tightness test device thereof |
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