CN115274174A - Nuclear fuel element irradiation test device - Google Patents
Nuclear fuel element irradiation test device Download PDFInfo
- Publication number
- CN115274174A CN115274174A CN202210893278.0A CN202210893278A CN115274174A CN 115274174 A CN115274174 A CN 115274174A CN 202210893278 A CN202210893278 A CN 202210893278A CN 115274174 A CN115274174 A CN 115274174A
- Authority
- CN
- China
- Prior art keywords
- irradiation
- nuclear fuel
- irradiation test
- capsule
- spring
- 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.)
- Granted
Links
- 238000012360 testing method Methods 0.000 title claims abstract description 62
- 239000003758 nuclear fuel Substances 0.000 title claims abstract description 34
- 239000002775 capsule Substances 0.000 claims abstract description 37
- 239000000446 fuel Substances 0.000 claims abstract description 33
- 238000007789 sealing Methods 0.000 claims description 5
- 238000012546 transfer Methods 0.000 abstract description 4
- 230000009286 beneficial effect Effects 0.000 abstract description 2
- 238000005253 cladding Methods 0.000 description 18
- 230000000903 blocking effect Effects 0.000 description 11
- 230000003139 buffering effect Effects 0.000 description 6
- 230000001052 transient effect Effects 0.000 description 6
- 238000013461 design Methods 0.000 description 5
- 238000009826 distribution Methods 0.000 description 5
- 239000008188 pellet Substances 0.000 description 5
- 235000017166 Bambusa arundinacea Nutrition 0.000 description 3
- 235000017491 Bambusa tulda Nutrition 0.000 description 3
- 241001330002 Bambuseae Species 0.000 description 3
- 235000015334 Phyllostachys viridis Nutrition 0.000 description 3
- 239000011425 bamboo Substances 0.000 description 3
- 239000002826 coolant Substances 0.000 description 3
- 239000001307 helium Substances 0.000 description 3
- 229910052734 helium Inorganic materials 0.000 description 3
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 3
- 230000009471 action Effects 0.000 description 2
- 238000010586 diagram Methods 0.000 description 2
- 239000007789 gas Substances 0.000 description 2
- 238000000034 method Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 230000000712 assembly Effects 0.000 description 1
- 238000000429 assembly Methods 0.000 description 1
- 230000004323 axial length Effects 0.000 description 1
- 238000005520 cutting process Methods 0.000 description 1
- 230000007547 defect Effects 0.000 description 1
- 230000000694 effects Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000006872 improvement Effects 0.000 description 1
- 230000003993 interaction Effects 0.000 description 1
- 238000003754 machining Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000000452 restraining effect Effects 0.000 description 1
- 229910001220 stainless steel Inorganic materials 0.000 description 1
- 239000010935 stainless steel Substances 0.000 description 1
- 230000008961 swelling Effects 0.000 description 1
- 238000003466 welding Methods 0.000 description 1
Images
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21K—TECHNIQUES FOR HANDLING PARTICLES OR IONISING RADIATION NOT OTHERWISE PROVIDED FOR; IRRADIATION DEVICES; GAMMA RAY OR X-RAY MICROSCOPES
- G21K5/00—Irradiation devices
- G21K5/10—Irradiation devices with provision for relative movement of beam source and object to be irradiated
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21K—TECHNIQUES FOR HANDLING PARTICLES OR IONISING RADIATION NOT OTHERWISE PROVIDED FOR; IRRADIATION DEVICES; GAMMA RAY OR X-RAY MICROSCOPES
- G21K5/00—Irradiation devices
-
- 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)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
The invention discloses a nuclear fuel element irradiation test device, relates to the technical field of nuclear fuel elements of reactors, solves the problem that the pressure and temperature environment in an irradiation test cannot be controlled in the prior art, has the beneficial effects of adjusting the heat transfer performance of the irradiation device and reducing the local structural rigidity, and has the following specific scheme: the utility model provides a nuclear fuel element irradiation test device, includes the irradiation capsule, is located inside the irradiation capsule and with irradiation capsule coaxial setting to the split cover, has the space that holds the irradiation test piece to split cover inside, sets up spring fin between split cover and the irradiation capsule inner wall, and irradiation capsule top sets up first air cavity and grows with the thermal energy and the irradiation that hold the fuel rod, and first air cavity top sets up the end plug, and the end plug sets up the gas charging hole.
Description
Technical Field
The invention relates to the technical field of nuclear fuel elements of reactors, in particular to a nuclear fuel element irradiation test device.
Background
The statements in this section merely provide background information related to the present disclosure and may not constitute prior art.
The fuel assemblies are the nuclear "core" of the reactor and a source of heat. In order to improve the competitiveness of nuclear power plants, it is necessary to further increase the burnup of the fuel to improve economy, but the swelling of fuel pellets at high burnup will cause cladding-pellet mechanical action, resulting in fuel rod leakage. When power is increased, the cladding stresses increase due to thermal expansion of the fuel pellets, closing of the cladding pellet gap, pellet contact with the cladding, possibly resulting in excessive cladding stresses and failure, especially when the target burn-up is high, the primary cause of cladding failure is the interaction (PCM I) resulting from cladding and fuel contact. To study the core-cladding contact state at higher burnup, it was necessary to develop a fuel rod power transient test in the study stack. The inventor finds that the external boundary pressure and temperature conditions of the fuel rod are difficult to keep consistent with the normal operation working condition of the pressurized water reactor when the power transient test of the fuel rod is carried out in the existing pool reactor, and the pressure and temperature environment in the irradiation test cannot be controlled.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide a nuclear fuel element irradiation test device, which solves the technical problem that the consistency of the external boundary pressure and temperature conditions of a fuel rod and the normal operation working condition of a pressurized water reactor is difficult to realize in the prior art.
In order to achieve the purpose, the invention is realized by the following technical scheme:
the utility model provides a nuclear fuel element irradiation test device, includes the irradiation capsule, is located irradiation capsule inside and with the coaxial setting of irradiation capsule to the split sleeve, has the space that holds the irradiation test piece to split sleeve inside, sets up spring fin between split sleeve and the irradiation capsule inner wall, and irradiation capsule top sets up the thermal expansion and the irradiation growth of first air cavity in order to hold the fuel rod in the irradiation test piece, and first air cavity top sets up the end plug, and the end plug sets up the gas charging hole.
According to the irradiation test device, the spring fins are designed in the irradiation capsule, the whole strength of the structure is guaranteed, the purpose that the contact pressure of the cladding tube during the fuel rod power transient test reaches the in-core coolant pressure range during normal operation is achieved by reducing the local structural rigidity, and the contact pressure distribution of the fuel rod cladding tube can be more uniform due to the sleeved design.
According to the nuclear fuel element irradiation test device, the irradiation capsule main body structure is a central cylinder, the spring fins are arranged between the split sleeve and the inner wall of the central cylinder, and the spring fins and the split sleeve are of an integrated structure.
According to the nuclear fuel element irradiation test device, the plurality of spring fins are arranged along the circumferential direction of the inner wall of the irradiation capsule, the single spring fin is of an S-shaped structure, and the plurality of spring fins form a central symmetry structure or an axial symmetry structure.
According to the irradiation test device for the nuclear fuel element, the bottom of the irradiation capsule is provided with the second air cavity, and the first air cavity and the second air cavity are respectively positioned at the upper end and the lower end of the split sleeve.
According to the nuclear fuel element irradiation test device, the lower end plug is arranged at the second air cavity for sealing, and the upper surface of the lower end plug supports the bottom of the irradiation test piece.
According to the irradiation test device for the nuclear fuel element, the upper end plug and the lower end plug are both in a stepped cylindrical structure.
According to the nuclear fuel element irradiation test device, the split sleeve is of a two-piece split structure, and the inner side and the outer side of the split sleeve are tightly attached to the fuel rod and the spring fin respectively.
According to the nuclear fuel element irradiation test device, the spring fins are S-shaped through the radial baffle plates, and the number of the radial baffle plates is at least two.
According to the nuclear fuel element irradiation test device, the first air cavity and the second air cavity are coaxially arranged with the split sleeve.
According to the nuclear fuel element irradiation test device, the upper end face of the lower end plug is flush with the lower end face of the spring fin, and the lower end face of the upper end plug is flush with the upper end face of the spring fin.
The beneficial effects of the invention are as follows:
1. according to the invention, the spring fins are designed in the irradiation capsule, so that the whole strength of the structure is ensured, the aim that the contact pressure of the cladding tube during the fuel rod power transient test reaches the in-reactor coolant pressure range during normal operation is fulfilled by reducing the local structural rigidity, and the contact pressure distribution of the fuel rod cladding tube can be more uniform by the aid of the sleeving design.
2. The heat transfer performance of the irradiation device can be adjusted by designing spring fins, split sleeves and upper end plugs with axisymmetric structures or centrosymmetric structures in the irradiation capsule and simultaneously opening inflation holes, and filling helium into the irradiation capsule, so that the temperature of the cladding tube of the irradiation test piece reaches the cladding temperature range in normal operation.
Drawings
The accompanying drawings, which are incorporated in and constitute a part of this specification, are included to provide a further understanding of the invention, and are incorporated in and constitute a part of this specification, illustrate exemplary embodiments of the invention and together with the description serve to explain the invention and not to limit the invention.
FIG. 1 is a cross-sectional view of an irradiation capsule in a nuclear fuel element irradiation testing apparatus according to the present invention.
Fig. 2 is a top view of an irradiation capsule in a nuclear fuel element irradiation test apparatus according to the present invention.
Fig. 3 is a schematic diagram of a first arrangement of spring fins in a nuclear fuel element irradiation testing apparatus according to the present invention.
Fig. 4 is a schematic diagram of a second arrangement of spring fins in a nuclear fuel element irradiation testing apparatus according to the present invention.
In the figure: the spacing or dimensions between each other are exaggerated to show the location of the various parts, and the schematic is shown only schematically.
Wherein: 1. the spring fin comprises a central cylinder, 2 radial baffle plates, 2-1 first supporting parts, 2-2 first matching parts, 2-3 second matching parts, 2-4 second supporting parts, 2-5 third matching parts, 2-6 fourth matching parts, 3 upper end plugs, 4 lower end plugs, 5 split sleeves and 6 spring fins.
Detailed Description
It is to be understood that the following detailed description is exemplary and is intended to provide further explanation of the invention as claimed. Unless defined otherwise, all technical and scientific terms used herein have the same meaning as commonly understood by one of ordinary skill in the art to which this invention belongs.
As described in the background of the invention, the problem that the external boundary pressure and temperature conditions of the fuel rod are consistent with the normal operation condition of the pressurized water reactor is difficult to realize in the prior art, and in order to solve the technical problem, the invention provides a nuclear fuel element irradiation test device.
Example one
In an exemplary embodiment of the present invention, referring to fig. 1 to 4, a nuclear fuel element irradiation test device includes an irradiation capsule, a split sleeve 5 disposed inside the irradiation capsule and coaxially disposed with the irradiation capsule, and an irradiation test piece disposed inside the split sleeve 5. The irradiation test piece is of a cylindrical structure, and a fuel rod is arranged inside the irradiation test piece.
Specifically, the irradiation capsule major structure is a center section of thick bamboo 1, and center section of thick bamboo 1 is made through machining by the rod, for cylindrical structure, and the irradiation capsule is center section of thick bamboo top and sets up first air cavity promptly, and the bottom sets up the second air cavity, and first air cavity and second air cavity and the coaxial setting of split cover. The first air cavity and the second air cavity are respectively positioned at the upper end and the lower end of the split sleeve, the spring fin 6 is arranged in the middle of the inner wall of the central cylinder, and the spring fin 6 is arranged between the split sleeve and the inner wall of the central cylinder to relieve the contact pressure of the outer surface of the fuel element test piece. The spring fins and the central cylinder are of an integrated structure, so that the stability of the spring fins 6 can be guaranteed, and the buffering effect of the spring fins 6 can be exerted.
The spring fins 6 are located inside the central cylinder and are machined by wire cutting, and the arrangement of the springs is shown in fig. 2-4. The height of the spring fin 6 of the embodiment is 400mm, the wall thickness of the spring fin is 1.1mm specifically according to the length of a test piece, and the number of the springs is 8 in total along the circumferential direction of the central cylinder.
The first air cavity is located at the top of the spring fin 6, the second air cavity is located at the bottom of the spring fin 6, and the first air cavity and the second air cavity are used for accommodating thermal expansion and irradiation growth of the fuel rod and accommodating release of radioactive fission products in the fuel rod, which may occur in the transient power test process. The top of the first air cavity is provided with an upper end plug for sealing, and the upper end plug 3 is provided with an inflation hole for filling helium gas, so that the internal heat transfer of the irradiation capsule is adjusted.
The second air cavity is provided with a lower end plug for sealing, and the upper surface of the lower end plug 4 supports the bottom of the irradiation test piece. The upper end plug and the lower end plug are both in a stepped cylindrical structure. The upper end plug 3 and the lower end plug 4 are connected with the central cylinder 1 in a welding mode, the sealing of the structure is kept, the lower end plug plays a role in axially positioning the irradiation test piece, the upper end face of the lower end plug is flush with the lower end face of the spring fin, and the lower end face of the upper end plug 3 is flush with the upper end face of the spring fin.
In the test process, the thermal expansion of the irradiation test piece is considered, so that the contact pressure of the outer surface of the fuel element is increased, the spring fins 6 are designed into an S-shaped structure, the rigidity of a local structure can be effectively reduced, the contact pressure of the outer surface of the irradiation test piece is adjusted, and in order to enable the contact pressure to be distributed more uniformly, the spring fins are arranged in the irradiation capsule in an axisymmetric mode. The radial stop limits the shape of the spring fin to an S-shape. The number of layers and the thickness of the radial baffle plates of the spring fins 6 can be adjusted according to the contact pressure of the fuel rods required by the test, but the number of layers of the radial baffle plates of the spring fins 6 is at least two, and the axial length of the spring fins can be adjusted according to the size of the test piece.
In another example, the spring fins 6 are arranged in a central symmetrical configuration.
In the structural form of central symmetry of the spring fins, as shown in fig. 3, the radial blocking pieces 2 limit the spring fins to be in a central symmetrical structure in the outer circumferential direction of the split sleeve, and the spring fins are eight, specifically, the radial blocking pieces comprise a first supporting portion 2-1, a first matching portion 2-2 and a second matching portion 2-3, because the split sleeve 5 is a two-piece split structure, as seen from fig. 3, the split sleeve is divided into an upper piece and a lower piece, the eight radial blocking pieces with the same structure are distributed on the outer circumferential side of the split sleeve, the eight radial blocking pieces 2 and the eight spring fins are distributed in a staggered manner, each piece is matched with the four spring fins, and the four radial blocking pieces, the first supporting portion 2-1 of the radial blocking piece and the split sleeve are vertically and fixedly arranged, the tail end of the first supporting portion is fixed at one end of the first matching portion, the first matching portion is of an arc-shaped structure and extends in the counterclockwise direction, a gap is formed between the extending tail end of the first matching portion 2-2 and the adjacent first supporting portion 2-1 and used for accommodating a spring fin type body, an S structure of the spring fins is maintained, and the stability of the spring fins is also ensured, and the stability of the spring fins is exerted.
The middle position of the first supporting part 2-1 body is connected with one end of the second matching part, the extending direction of the second matching part is opposite to the extending direction of the first matching part, the first matching part extends anticlockwise, the second matching part extends clockwise, a gap is formed between the extending end of the second matching part and the adjacent first supporting part body, the gap is used for passing through the spring fin, the effects of the second matching part and the first matching part play a role in fixing and limiting the spring fin, good elasticity of the spring fin is guaranteed, the stress is stable, buffering when the split sleeve is split is realized, and the pressure is adjusted to a normal value.
The eight spring fins in fig. 3 are in a central symmetrical structure, and can effectively and uniformly buffer the pressure caused by sleeve opening.
In another example, the spring fin is in an axisymmetric structural form as shown in fig. 4, the radial blocking pieces include second supporting portions 2-4, third matching portions 2-5 and fourth matching portions 2-6, the second supporting portions 2-4 are also vertically fixed on the outer wall surfaces of the split sleeves, the third matching portions 2-5 are also arranged in an arc shape, the tops of the second supporting portions 2-4 support the middle positions of the third matching portions, the third matching portions are connected with the second supporting portions in a symmetrical structure, the fourth matching portions 2-6 are arranged between every two adjacent second supporting portions, the fourth matching portions include supporting blocking pieces vertically fixed on the outer wall surfaces of the split sleeves, the length of the supporting blocking pieces is smaller than that of the second supporting portions, the middle positions of the supporting blocking pieces extend in an arc shape towards the clockwise direction and the counterclockwise direction, the fourth matching portions are also in a symmetrical structure, four fourth buffering portions and four second supporting portions are respectively arranged, the fourth buffering portions and the second supporting portions are also in a staggered distribution, and the eight radial blocking pieces are matched with the spring fin, so that the structure of the spring fin is limited to be in an S shape and exert a stable buffering effect.
Through the axisymmetric structural design form of the spring fins, the uniform buffering of the pressure brought by the sleeve opening can be realized in the radial direction of the spring fins.
It can be understood that, in the centrosymmetric structure of fig. 3, the opening directions of the eight S-shaped spring fins are distributed clockwise along the circumference, and in the axisymmetric structure of fig. 4, the opening directions of the eight S-shaped spring fins are arranged opposite to each other two by two.
The split sleeve 5 of the embodiment is a stainless steel split sleeve, and is machined, the outer diameter of the split sleeve is in surface contact with the spring fin 6, the inner diameter of the split sleeve is the same as the outer diameter of the fuel rod, and the split sleeve is tightly attached to the fuel rod and the spring fin 6. The inside and the outside of the split sleeve 5 are respectively and tightly attached to the fuel rod and the spring fin. The split sleeve 5 of the two-petal split structure does not play a role in restraining the radial thermal expansion of the fuel rod, and the contact pressure distribution of the fuel rod cladding tube can be more uniform by matching with the buffer action of the spring fin 6.
Through irradiation capsule internal design spring fin 6, when guaranteeing the structure bulk strength, through reducing local structural rigidity when having realized that the contact pressure of cladding pipe reaches the purpose of the in-pile coolant pressure scope of normal operating when fuel rod power transient test, to the design of uncapping, can make the contact pressure distribution of fuel rod cladding pipe more even.
In addition, spring fins, the split sleeves and the upper end plugs are designed in the irradiation capsules, the air filling holes are simultaneously formed in the upper end plugs, helium is filled in the irradiation capsules, the heat transfer performance of the irradiation device can be adjusted, and the temperature of the irradiation test piece cladding tube reaches the cladding temperature range in normal operation.
The above description is only a preferred embodiment of the present invention and is not intended to limit the present invention, and various modifications and changes may be made by those skilled in the art. Any modification, equivalent replacement, or improvement made within the spirit and principle of the present invention should be included in the protection scope of the present invention.
Claims (10)
1. The utility model provides a nuclear fuel element irradiation test device, its characterized in that includes the irradiation capsule, is located inside the irradiation capsule and sets up with the irradiation capsule is coaxial to the split cover, has the space that holds the irradiation test piece to split cover inside, sets up the spring fin between split cover and the irradiation capsule inner wall, and irradiation capsule top sets up first air cavity in order to hold the thermal energy and the irradiation growth of the fuel rod in the irradiation test piece, and first air cavity top sets up the end plug, and the end plug sets up the gas charging hole.
2. The nuclear fuel element irradiation test device of claim 1, wherein the irradiation capsule main body structure is a central cylinder, the spring fin is arranged between the split sleeve and the inner wall of the central cylinder, and the spring fin and the split sleeve are of an integrated structure.
3. The nuclear fuel element irradiation test device according to claim 1, wherein a plurality of spring fins are arranged along the circumferential direction of the inner wall of the irradiation capsule, the structure of a single spring fin is S-shaped, and a plurality of spring fins form a central symmetry structure or an axial symmetry structure.
4. The irradiation test device of nuclear fuel elements according to claim 1, wherein a second air cavity is provided at the bottom of the irradiation capsule, and the first air cavity and the second air cavity are respectively located at the upper end and the lower end of the split sleeve.
5. The nuclear fuel element irradiation test device according to claim 4, wherein a lower end plug is arranged at the second air cavity for sealing, and the upper surface of the lower end plug supports the bottom of the irradiation test piece.
6. The irradiation test apparatus for nuclear fuel elements as claimed in claim 5, wherein the upper end plug and the lower end plug are both of stepped cylindrical structure.
7. The irradiation test device for nuclear fuel elements as claimed in claim 1, wherein the split sleeve is a two-piece split structure, and the inside and the outside of the split sleeve are respectively closely attached to the fuel rod and the spring fin.
8. The irradiation test apparatus for nuclear fuel elements as claimed in claim 3, wherein the spring fin is formed in an S-shape by fitting radial blades having at least two layers.
9. The nuclear fuel element irradiation test device according to claim 4, wherein the first air chamber and the second air chamber are provided coaxially with the split sleeve.
10. The irradiation test apparatus for nuclear fuel elements as claimed in claim 5, wherein the upper end surface of the lower end plug is flush with the lower end surface of the spring fin, and the lower end surface of the upper end plug is flush with the upper end surface of the spring fin.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210893278.0A CN115274174B (en) | 2022-07-27 | 2022-07-27 | Nuclear fuel element irradiation test device |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN202210893278.0A CN115274174B (en) | 2022-07-27 | 2022-07-27 | Nuclear fuel element irradiation test device |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN115274174A true CN115274174A (en) | 2022-11-01 |
| CN115274174B CN115274174B (en) | 2024-05-31 |
Family
ID=83771592
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN202210893278.0A Active CN115274174B (en) | 2022-07-27 | 2022-07-27 | Nuclear fuel element irradiation test device |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN115274174B (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115831414A (en) * | 2022-11-24 | 2023-03-21 | 中国核动力研究设计院 | High-temperature irradiation test device suitable for granular fuel |
Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0704858A1 (en) * | 1994-09-29 | 1996-04-03 | Siemens Power Corporation | Nuclear fuel assembly with extruded active height for a pressurized water reactor |
| US20050105667A1 (en) * | 2003-07-31 | 2005-05-19 | Bong Goo Kim | Instrumented capsule for nuclear fuel irradiation tests in research reactors |
| KR100878330B1 (en) * | 2007-08-06 | 2009-01-14 | 한국원자력연구원 | Plug type research reactor irradiation rig |
| CN102867554A (en) * | 2012-09-19 | 2013-01-09 | 中国核动力研究设计院 | Modular bushing type irradiation in-pile verification device |
| CN110600150A (en) * | 2019-09-19 | 2019-12-20 | 中国核动力研究设计院 | Irradiation test device for metal type fast reactor fuel element |
| CN111477370A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Bulging explosion test device for outer casing of pressure-bearing annular fuel rod |
-
2022
- 2022-07-27 CN CN202210893278.0A patent/CN115274174B/en active Active
Patent Citations (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| EP0704858A1 (en) * | 1994-09-29 | 1996-04-03 | Siemens Power Corporation | Nuclear fuel assembly with extruded active height for a pressurized water reactor |
| US20050105667A1 (en) * | 2003-07-31 | 2005-05-19 | Bong Goo Kim | Instrumented capsule for nuclear fuel irradiation tests in research reactors |
| KR100878330B1 (en) * | 2007-08-06 | 2009-01-14 | 한국원자력연구원 | Plug type research reactor irradiation rig |
| CN102867554A (en) * | 2012-09-19 | 2013-01-09 | 中国核动力研究设计院 | Modular bushing type irradiation in-pile verification device |
| CN110600150A (en) * | 2019-09-19 | 2019-12-20 | 中国核动力研究设计院 | Irradiation test device for metal type fast reactor fuel element |
| CN111477370A (en) * | 2020-05-25 | 2020-07-31 | 中国原子能科学研究院 | Bulging explosion test device for outer casing of pressure-bearing annular fuel rod |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN115831414A (en) * | 2022-11-24 | 2023-03-21 | 中国核动力研究设计院 | High-temperature irradiation test device suitable for granular fuel |
Also Published As
| Publication number | Publication date |
|---|---|
| CN115274174B (en) | 2024-05-31 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| US4994233A (en) | Fuel rod with axial regions of annular and standard fuel pellets | |
| CN101223607B (en) | Advanced gray rod control assembly | |
| US20080084957A1 (en) | Nuclear reactor fuel assemblies | |
| US11495363B2 (en) | Small modular mobile fission reactor | |
| CN115274174B (en) | Nuclear fuel element irradiation test device | |
| US20090034674A1 (en) | Nuclear reactor control rod | |
| EP0290865A2 (en) | Nuclear reactor core containing fuel assemblies positioned adjacent core baffle structure | |
| CN110867261B (en) | Multi-type pellet mixed loading metal cooling reactor and management method | |
| JP6666072B2 (en) | Fuel rods and fuel assemblies | |
| CN110867262A (en) | Liquid metal cooling reactor based on improvement of fuel utilization rate and management method | |
| CN113270206A (en) | Small-sized prismatic annular gas-cooled micro-reactor core system with densely arranged coolant channels | |
| US9136025B2 (en) | Dual-cooled fuel rod's spacer grids with upper and lower cross-wavy-shape dimple | |
| CN111081390B (en) | Double-clad fuel element with enhanced moderating capability | |
| US4294660A (en) | Spacer assembly retainer arrangement | |
| CN111276265A (en) | Rod-type fuel element using uranium-yttrium hydride fuel | |
| CA1083270A (en) | Fuel assembly spacer | |
| KR100912679B1 (en) | An annular nuclear fuel rod comprising annular-structure fuel pellets with axial incisions | |
| US11289211B2 (en) | Method of installing an external dashpot tube around a control rod guide tube in a nuclear fuel assembly | |
| CN110853770B (en) | Single-flow supercritical water-cooled reactor based on regular hexagonal fuel assembly | |
| GB2154046A (en) | Radial neutron reflector | |
| WO2016053609A2 (en) | Nuclear fuel element corrugated plenum holddown device | |
| EP4343791A1 (en) | A fuel assembly, a follower comprising a fuel assembly and a nuclear reactor | |
| CN212874072U (en) | Test device for bulging and blasting of cladding in pressure-bearing annular fuel rod | |
| CN109935361B (en) | Square double-sided cooling annular fuel assembly | |
| CN117012422A (en) | Assembling process method of solid reactor core fuel element and fuel element |
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 | ||
| CB02 | Change of applicant information |
Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd. Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd. |
|
| CB02 | Change of applicant information | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |