CN114944234A - End plug cladding integrated annular fuel rod and fuel assembly - Google Patents
End plug cladding integrated annular fuel rod and fuel assembly Download PDFInfo
- Publication number
- CN114944234A CN114944234A CN202210466888.2A CN202210466888A CN114944234A CN 114944234 A CN114944234 A CN 114944234A CN 202210466888 A CN202210466888 A CN 202210466888A CN 114944234 A CN114944234 A CN 114944234A
- Authority
- CN
- China
- Prior art keywords
- cladding
- end plug
- fuel rod
- core block
- annular fuel
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Pending
Links
- 238000005253 cladding Methods 0.000 title claims abstract description 101
- 239000000446 fuel Substances 0.000 title claims abstract description 65
- 238000003466 welding Methods 0.000 claims abstract description 15
- 238000004519 manufacturing process Methods 0.000 claims description 7
- 125000006850 spacer group Chemical group 0.000 claims 1
- 230000000712 assembly Effects 0.000 abstract description 2
- 238000000429 assembly Methods 0.000 abstract description 2
- 239000008188 pellet Substances 0.000 description 28
- 238000000034 method Methods 0.000 description 11
- 230000002285 radioactive effect Effects 0.000 description 4
- 239000003758 nuclear fuel Substances 0.000 description 3
- 239000002826 coolant Substances 0.000 description 2
- 238000012545 processing Methods 0.000 description 2
- 239000012857 radioactive material Substances 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 230000009286 beneficial effect Effects 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000007689 inspection Methods 0.000 description 1
- 239000000463 material Substances 0.000 description 1
- 239000002184 metal Substances 0.000 description 1
- 238000012805 post-processing Methods 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 239000004449 solid propellant Substances 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
Images
Classifications
-
- 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
-
- 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
- G21C3/16—Details of the construction within the casing
-
- 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
-
- 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)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention belongs to the technical field of fuel assemblies, and particularly relates to an end plug and cladding integrated annular fuel rod and a fuel assembly. The core block is composed of an outer casing, an inner cladding and a core block, wherein one end of the outer casing is provided with an integrally formed upper end plug, and one end of the inner cladding is provided with an integrally formed lower end plug; the inner wall of the outer cladding is contacted with the outer wall of the core block, the outer wall of the inner cladding is contacted with the inner wall of the core block, the core block is stacked between the outer cladding and the inner cladding, the stacked core blocks are in a long-strip cylindrical shape, the upper end face of the cylindrical core block is contacted with the lower surface of the upper end plug of the outer cladding, the lower end face of the cylindrical core block is contacted with the upper surface of the lower end plug of the inner cladding, and a sealed chamber is formed between the outer cladding and the inner cladding after welding. The invention improves the assembly efficiency of the annular fuel rod and the efficiency of post-treatment.
Description
Technical Field
The invention belongs to the technical field of fuel assemblies, and particularly relates to an end plug and cladding integrated annular fuel rod and a fuel assembly.
Background
During the operation of a nuclear power plant reactor, the performance of nuclear fuel is an important factor affecting the safety and economy of the reactor. Therefore, the research on fuel elements is put on a very prominent position internationally, and various performances of the nuclear fuel elements are continuously improved by optimizing the design of the fuel elements, adopting advanced structural materials, improving element manufacturing processes and other methods, so that nuclear power is promoted to develop towards a safer and more economic direction.
In existing pressurized water reactor fuel assembly designs, the fuel rods are generally solid in shape and consist of cladding, pellets, springs, upper and lower end plugs. The cladding acts as a cladding for the fuel core and contains the radioactive material produced by the core during operation so that it does not release the radioactive material into the primary circuit under normal operating conditions. Compared with a solid fuel rod, the annular fuel rod has an annular cross section and is provided with an inner coolant channel and an outer coolant channel. At present, an annular fuel rod mainly comprises an inner cladding, an outer cladding, an annular pellet, a spring, an upper end plug and a lower end plug. The annular core block and the spring are assembled between the inner cladding and the outer cladding, and then the upper end plug and the lower end plug are welded on the inner cladding and the outer cladding to form a sealed annular rod for containing the core block under the normal operation condition.
In the process of assembling and processing the annular fuel rod, the process which is easy to rework and repair is the process of welding the fuel rod and the end plug. After the pellet tubulation is completed, if the welding failure of the fuel rod and the end plug occurs, the end plug may need to be cut off and reworked again. It may also be necessary to rework the pellet tubulation operation again. Therefore, the number of welding seams is reduced as much as possible, and the possibility of reworking during mass production can be reduced in terms of the number of processes.
For annular fuel rods with radioactivity prior to irradiation or annular target rods for isotope production, pellets before loading and products after loading may need to be processed in a hot chamber. If the rod structure is complex and difficult to assemble, the hot chamber operation assembly and the post-treatment are inconvenient. Thus, for this type of target, the simpler it is to assemble, the fewer the welds, and the greater ease in both pre-assembly and post-processing.
Therefore, the novel cladding end plug integrated annular fuel rod is designed, the defects of the prior art can be overcome, and the assembly efficiency and the post-treatment efficiency of the annular fuel rod are improved.
Disclosure of Invention
The invention aims to provide an end plug cladding integrated annular fuel rod and a fuel assembly, which can contain pellets and radioactive substances generated in the operation of the pellets.
In order to achieve the purpose, the technical scheme adopted by the invention is as follows:
an end plug and cladding integrated annular fuel rod comprises an outer casing, an inner casing and pellets, wherein an integrally-formed upper end plug is arranged at one end of the outer casing, and an integrally-formed lower end plug is arranged at one end of the inner casing; the inner wall of the outer cladding is contacted with the outer wall of the core block, the outer wall of the inner cladding is contacted with the inner wall of the core block, the core block is stacked between the outer cladding and the inner cladding, the stacked core blocks are in a long-strip cylindrical shape, the upper end face of the cylindrical core block is contacted with the lower surface of the upper end plug of the outer cladding, the lower end face of the cylindrical core block is contacted with the upper surface of the lower end plug of the inner cladding, and a sealed chamber is formed between the outer cladding and the inner cladding after welding.
The upper end plug is of a cylindrical structure.
The outer casing is a circular tube with a central symmetry.
The lower end plug is of a cylindrical structure.
The inner cladding is a circular tube with a central symmetry.
The cross-shaped structure is arranged on the inner hole of the lower end plug on the inner cladding.
The inner hole of the upper plug on the outer wrapping shell is provided with a turbulent flow structure.
The inner hole of the lower end plug on the inner cladding is provided with a turbulent flow structure.
A fuel assembly comprises a plurality of end plug cladding integrated annular fuel rods, an upper tube seat, a plurality of guide tubes, a positioning grid and a lower tube seat.
A production target comprises a plurality of end plug cladding integrated annular fuel rods, a hoisting head, an upper end fixing piece and a lower end fixing piece.
The beneficial effects obtained by the invention are as follows:
the invention can omit each welding seam at two ends of the annular fuel rod, can omit a procedure in the welding and inspection processes, and improves the reliability of the whole workpiece.
The welding position of the inner wrapping shell can be changed, and can be set as a circumferential weld or an end face weld according to requirements. To adapt to the design of the fuel rod under different application conditions.
This design facilitates the loading of pellets by the operator if the assembly of the fuel rod requires operation in a specific space, such as a hot chamber. Because of the fewer parts, post-irradiation processing operations, such as removal of pellets, etc., are also easier.
The invention has simple structure and can be manufactured by using metal printing and other technologies.
Drawings
FIG. 1 is a schematic diagram of an embodiment;
FIG. 2 is a schematic view of the second embodiment;
FIG. 3 is a schematic view of the third embodiment;
in the figure: 1. an outer envelope; 2. an inner envelope; 3. and (3) a core block.
Detailed Description
The invention is described in detail below with reference to the figures and specific embodiments.
The design of reducing two welding seams is adopted, the inner cladding is designed into a whole with one of the upper end plug and the lower end plug, and the outer cladding is designed into a whole with the rest end plugs, so that the manufacturing process of the annular fuel rod is greatly simplified, and meanwhile, the possibility of radioactive substance leakage from the welding seams is reduced.
An end plug and cladding integrated annular fuel rod consists of an outer cladding 1, an inner cladding 2 and pellets 3, wherein end plugs similar to the design of the fuel rod are arranged on the outer cladding 1 and the inner cladding 2;
the outer shell 1 is composed of a round tube matched with the core block 3, and the inner surface of the outer shell is contacted with the core block after being assembled; the inner cladding 2 consists of a circular tube adapted to the pellet 3, the outer surface of which is in contact with the pellet after assembly; the outer and inner shells form a cavity that can receive a core block.
The basic structure of the fuel assembly is composed of a plurality of integrated annular fuel rods, an upper tube seat, a plurality of guide tubes, a positioning grid and a lower tube seat.
The basic structure of the production target piece consists of a plurality of integrated annular fuel rods, a hoisting head, an upper end fixing piece and a lower end fixing piece.
Example one
The end plug and cladding integrated annular fuel rod consists of an outer cladding 1, an inner cladding 2 and pellets 3. The outer envelope 1 in this embodiment comprises in general terms an upper end plug and an outer envelope, which are integrated into one piece. The upper end plug of the annular fuel rod in general sense is of a cylindrical structure, and the outer wrapping shell is a circular tube with a central symmetry; the inner cladding 2 comprises a lower end plug and an inner cladding in a general sense, the lower end plug of the annular fuel rod in the general sense is of a cylindrical structure, and the inner cladding is a circular tube with a central symmetry; the inner wall of the outer envelope 1 is in contact with the outer wall of the core block 3 and the outer wall of the inner envelope 2 is in contact with the inner wall of the core block 3. The pellets 3 are stacked between the outer 1 and inner 2 cladding shells and after stacking the pellets are in the form of an elongated cylinder. The upper end face of the cylinder is in contact with the lower surface of the upper end plug of the outer envelope 1, and the lower end face of the cylinder is in contact with the upper surface of the lower end plug of the inner envelope 2. The inner and outer cladding forms a sealed chamber after welding, and the pellets and radioactive products generated in the operation process are contained in the chamber.
Example two
The end plug and cladding integrated annular fuel rod consists of an outer cladding 1, an inner cladding 2 and pellets 3. The outer envelope 1 in this embodiment comprises in general terms an upper end plug and an outer envelope, which are integrated. The upper end plug of the annular fuel rod in general sense is of a cylindrical structure, and the outer wrapping shell is a circular tube with a central symmetry; the inner cladding 2 comprises a lower end plug and an inner cladding in a general sense, the lower end plug of the annular fuel rod in the general sense is of a cylindrical structure, and the inner cladding is a circular tube with a central symmetry; the inner wall of the outer envelope 1 is in contact with the outer wall of the core block 3 and the outer wall of the inner envelope 2 is in contact with the inner wall of the core block 3. The pellets 3 are stacked between the outer 1 and inner 2 cladding shells and after stacking the pellets are in the form of an elongated cylinder. The upper end face of the cylinder is in contact with the lower surface of the upper end plug of the outer envelope 1, and the lower end face of the cylinder is in contact with the upper surface of the lower end plug of the inner envelope 2. The inner and outer cladding forms a sealed chamber after welding, and the pellets and radioactive products generated in the operation process are contained in the chamber.
Wherein, the inner hole of the lower end plug on the inner cladding 2 is provided with a cross structure which has the function of preventing foreign matters. The flow distribution of the inner and outer flow passages can be adjusted through the design of the structure.
EXAMPLE III
The end plug and cladding integrated annular fuel rod consists of an outer cladding 1, an inner cladding 2 and pellets 3. The outer envelope 1 in this embodiment comprises in general terms an upper end plug and an outer envelope, which are integrated. The upper end plug of the annular fuel rod in general sense is of a cylindrical structure, and the outer wrapping shell is a circular tube with a central symmetry; the inner cladding 2 comprises a lower end plug and an inner cladding in a general sense, the lower end plug of the annular fuel rod in the general sense is of a cylindrical structure, and the inner cladding is a circular tube with a central symmetry; the inner wall of the outer envelope 1 is in contact with the outer wall of the core block 3, and the outer wall of the inner envelope 2 is in contact with the inner wall of the core block 3. The pellets 3 are stacked between the outer 1 and inner 2 cladding shells, after stacking, in the form of elongated cylinders. The upper end face of the cylinder is in contact with the lower surface of the upper end plug of the outer envelope 1, and the lower end face of the cylinder is in contact with the upper surface of the lower end plug of the inner envelope 2. The inner and outer cladding forms a sealed chamber after welding, and the pellets and radioactive products generated in the operation process are contained in the chamber.
Wherein, the upper end plug inner hole on the outer casing 1 and the lower end plug inner hole on the inner casing 2 are provided with turbulent flow structures, and the heat exchange efficiency of the inner flow channel can be increased to a certain degree through the design of the structure.
Example four
The fuel assembly is composed of a plurality of end plug cladding integrated annular fuel rods, an upper tube seat, a plurality of guide tubes, a positioning grid and a lower tube seat. The integrated annular fuel rod in the embodiment comprises an outer cladding 1, an inner cladding 2 and a pellet 3. The outer envelope 1 comprises in general terms an upper end plug and an outer envelope, which are integrated into one piece. The upper end plug of the annular fuel rod in general sense is of a cylindrical structure, and the outer wrapping shell is a circular tube with a central symmetry; the inner cladding 2 comprises a lower end plug and an inner cladding in a general sense, the lower end plug of the annular fuel rod in the general sense is of a cylindrical structure, and the inner cladding is a circular tube with a central symmetry; the inner wall of the outer envelope 1 is in contact with the outer wall of the core block 3 and the outer wall of the inner envelope 2 is in contact with the inner wall of the core block 3. The pellets 3 are stacked between the outer 1 and inner 2 cladding shells and after stacking the pellets are in the form of an elongated cylinder. The upper end face of the cylinder is in contact with the lower surface of the upper end plug of the outer envelope 1, and the lower end face of the cylinder is in contact with the upper surface of the lower end plug of the inner envelope 2. The inner and outer cladding forms a sealed chamber after welding, and the pellets and radioactive products generated in the operation process are contained in the chamber. Wherein, the upper end plug inner hole on the outer casing 1 and the lower end plug inner hole on the inner casing 2 are provided with turbulent flow structures, and the heat exchange efficiency of the inner flow channel can be increased to a certain degree through the design of the structure.
Claims (10)
1. An end plug cladding integrated annular fuel rod characterized by: the core block is composed of an outer casing, an inner cladding and a core block, wherein one end of the outer casing is provided with an integrally formed upper end plug, and one end of the inner cladding is provided with an integrally formed lower end plug; the inner wall of the outer cladding is contacted with the outer wall of the core block, the outer wall of the inner cladding is contacted with the inner wall of the core block, the core block is stacked between the outer cladding and the inner cladding, the stacked core blocks are in a long-strip cylindrical shape, the upper end face of the cylindrical core block is contacted with the lower surface of the upper end plug of the outer cladding, the lower end face of the cylindrical core block is contacted with the upper surface of the lower end plug of the inner cladding, and a sealed chamber is formed between the outer cladding and the inner cladding after welding.
2. The end plug cladding integrated annular fuel rod of claim 1, wherein: the upper end plug is of a cylindrical structure.
3. The end plug cladding integrated annular fuel rod of claim 1, wherein: the outer casing is a circular tube with a central symmetry.
4. The end plug clad integrated annular fuel rod of claim 1, wherein: the lower end plug is of a cylindrical structure.
5. The end plug cladding integrated annular fuel rod of claim 1, wherein: the inner cladding is a circular tube with a central symmetry.
6. The end plug clad integrated annular fuel rod of claim 1, wherein: the cross-shaped structure is arranged on the inner hole of the lower end plug on the inner cladding.
7. The end plug cladding integrated annular fuel rod of claim 1, wherein: the inner hole of the upper end plug on the outer casing is provided with a turbulent flow structure.
8. The end plug cladding integrated annular fuel rod of claim 7, wherein: the inner hole of the lower end plug on the inner cladding is provided with a turbulent flow structure.
9. A fuel assembly, characterized by: the fuel rod comprises a plurality of annular fuel rods with integrated end plugs and cladding as claimed in any one of claims 1 to 8, an upper tube socket, a plurality of guide tubes, a spacer grid and a lower tube socket.
10. A production target, comprising: the fuel rod comprises a plurality of the end plug cladding integrated annular fuel rods as claimed in any one of claims 1 to 8, a hoisting head, an upper end fixing piece and a lower end fixing piece.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210466888.2A CN114944234A (en) | 2022-04-27 | 2022-04-27 | End plug cladding integrated annular fuel rod and fuel assembly |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210466888.2A CN114944234A (en) | 2022-04-27 | 2022-04-27 | End plug cladding integrated annular fuel rod and fuel assembly |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CN114944234A true CN114944234A (en) | 2022-08-26 |
Family
ID=82907637
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210466888.2A Pending CN114944234A (en) | 2022-04-27 | 2022-04-27 | End plug cladding integrated annular fuel rod and fuel assembly |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN114944234A (en) |
Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06273580A (en) * | 1993-03-19 | 1994-09-30 | Nuclear Fuel Ind Ltd | Fuel rod end plug welding method |
| JPH07229985A (en) * | 1994-02-21 | 1995-08-29 | Japan Nuclear Fuel Co Ltd<Jnf> | Sealed end plug of nuclear fuel rod |
| JPH1152087A (en) * | 1997-07-31 | 1999-02-26 | Toshiba Corp | Nuclear fuel clad and its production |
| KR20080019876A (en) * | 2006-08-29 | 2008-03-05 | 한국원자력연구원 | Upper and lower end plug of an annular nuclear fuel rod |
| KR20130073368A (en) * | 2011-12-23 | 2013-07-03 | 한국원자력연구원 | A lower end plug with a debris filter for a dual-cooled annular fuel |
| CN105706176A (en) * | 2013-09-16 | 2016-06-22 | 西屋电气有限责任公司 | A sic matrix fuel cladding tube with spark plasma sintered end plugs |
| CN106356107A (en) * | 2016-11-11 | 2017-01-25 | 上海核工程研究设计院 | Additively manufactured spent fuel storage grillage |
| US20180102192A1 (en) * | 2016-10-11 | 2018-04-12 | Bwxt Nuclear Energy, Inc. | Resistance pressure weld for nuclear reactor fuel rod tube end plug |
| CN109935358A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of annular fuel rod limiting pellet axial float using spring |
| CN111477354A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Co-extrusion annular fuel rod |
| CN111968760A (en) * | 2020-08-26 | 2020-11-20 | 西安交通大学 | Nuclear fuel assembly positioning grid frame based on additive manufacturing technology |
| CN112786224A (en) * | 2020-12-31 | 2021-05-11 | 中核北方核燃料元件有限公司 | Method for connecting silicon carbide composite fuel cladding and end plug |
| CN114005552A (en) * | 2021-10-28 | 2022-02-01 | 中国核动力研究设计院 | Heat pipe reactor integrated solid reactor core structure capable of easily measuring reactor core temperature |
| CN114083102A (en) * | 2021-11-29 | 2022-02-25 | 中国原子能科学研究院 | Fuel target and welding method thereof |
-
2022
- 2022-04-27 CN CN202210466888.2A patent/CN114944234A/en active Pending
Patent Citations (14)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPH06273580A (en) * | 1993-03-19 | 1994-09-30 | Nuclear Fuel Ind Ltd | Fuel rod end plug welding method |
| JPH07229985A (en) * | 1994-02-21 | 1995-08-29 | Japan Nuclear Fuel Co Ltd<Jnf> | Sealed end plug of nuclear fuel rod |
| JPH1152087A (en) * | 1997-07-31 | 1999-02-26 | Toshiba Corp | Nuclear fuel clad and its production |
| KR20080019876A (en) * | 2006-08-29 | 2008-03-05 | 한국원자력연구원 | Upper and lower end plug of an annular nuclear fuel rod |
| KR20130073368A (en) * | 2011-12-23 | 2013-07-03 | 한국원자력연구원 | A lower end plug with a debris filter for a dual-cooled annular fuel |
| CN105706176A (en) * | 2013-09-16 | 2016-06-22 | 西屋电气有限责任公司 | A sic matrix fuel cladding tube with spark plasma sintered end plugs |
| US20180102192A1 (en) * | 2016-10-11 | 2018-04-12 | Bwxt Nuclear Energy, Inc. | Resistance pressure weld for nuclear reactor fuel rod tube end plug |
| CN106356107A (en) * | 2016-11-11 | 2017-01-25 | 上海核工程研究设计院 | Additively manufactured spent fuel storage grillage |
| CN109935358A (en) * | 2017-12-19 | 2019-06-25 | 中国原子能科学研究院 | A kind of annular fuel rod limiting pellet axial float using spring |
| CN111477354A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Co-extrusion annular fuel rod |
| CN111968760A (en) * | 2020-08-26 | 2020-11-20 | 西安交通大学 | Nuclear fuel assembly positioning grid frame based on additive manufacturing technology |
| CN112786224A (en) * | 2020-12-31 | 2021-05-11 | 中核北方核燃料元件有限公司 | Method for connecting silicon carbide composite fuel cladding and end plug |
| CN114005552A (en) * | 2021-10-28 | 2022-02-01 | 中国核动力研究设计院 | Heat pipe reactor integrated solid reactor core structure capable of easily measuring reactor core temperature |
| CN114083102A (en) * | 2021-11-29 | 2022-02-25 | 中国原子能科学研究院 | Fuel target and welding method thereof |
Non-Patent Citations (5)
| Title |
|---|
| 何晓军;韩智杰;代季高;明春;关玺彤;程全;: "环形燃料研发进展", ANNUAL REPORT OF CHINA INSTITUTE OF ATOMIC ENERGY, no. 00 * |
| 冯海宁;赵瑞瑞;王虹;史宝磊;何晓军: "压水堆环形燃料组件研发综述", 中国核电, no. 006 * |
| 季松涛;何晓军;: "环形燃料元件关键技术研究进展", 中国原子能科学研究院年报, no. 00 * |
| 季松涛;韩智杰;何晓军;李卓群;: "压水堆环形燃料组件研发进展", 原子能科学技术, no. 1 * |
| 韩智杰;孙雪霆;何晓军;: "环形燃料研发项目研究进展", 中国原子能科学研究院年报, no. 00 * |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JP2860377B2 (en) | Foreign matter filter lower nozzle in fuel assembly | |
| GB2258419A (en) | Fuel rod end plug welding method and end face trepan configuration | |
| KR101596431B1 (en) | Nuclear reactor green and sintered fuel pellets, corresponding fuel rod and fuel assembly | |
| US2984613A (en) | Fuel element for nuclear reactors | |
| CN111477370A (en) | Bulging explosion test device for outer casing of pressure-bearing annular fuel rod | |
| US8891724B2 (en) | Dual-cooled nuclear fuel rod having annular plugs and method of manufacturing the same | |
| CN114944234A (en) | End plug cladding integrated annular fuel rod and fuel assembly | |
| KR101640942B1 (en) | Nuclear reactor fuel assembly | |
| US20130272483A1 (en) | Lower end plug with temperature reduction device and nuclear reactor fuel rod including same | |
| CN212675929U (en) | Annular fuel cladding test piece capable of heating inside and outside simultaneously | |
| CN212874072U (en) | Test device for bulging and blasting of cladding in pressure-bearing annular fuel rod | |
| CN212675928U (en) | Bulging explosion test device for outer casing of pressure-bearing annular fuel rod | |
| CN111477368A (en) | Annular fuel cladding test piece capable of heating inside and outside simultaneously | |
| KR102460094B1 (en) | Bottom spacer grid of a nuclear fuel assembly | |
| US6697448B1 (en) | Neutronic fuel element fabrication | |
| GB2553090A (en) | Method of manufacture | |
| US20030016777A1 (en) | TIG welded MOX fuel rod | |
| KR20220028263A (en) | Inconel spacer grid of a nuclear fuel assembly | |
| WO2022093064A1 (en) | Fuel rod of a water-cooled water-moderated nuclear reactor | |
| CN103299371B (en) | Nuclear fuel rod plenum chamber spring assembly | |
| US4783312A (en) | Radial neutron refelector | |
| KR102250055B1 (en) | Spacer grid of a nuclear fuel assembly | |
| KR102465708B1 (en) | Bottom spacer grid of a nuclear fuel assembly | |
| CN117012422A (en) | Assembling process method of solid reactor core fuel element and fuel element | |
| WO2018132194A1 (en) | Control rod guide assembly with enhanced stiffness, fuel assembly including the same, and method of installing control rod guide assembly |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination |