CN112599266A - Spent fuel storage grillwork - Google Patents

Spent fuel storage grillwork Download PDF

Info

Publication number
CN112599266A
CN112599266A CN202011329810.3A CN202011329810A CN112599266A CN 112599266 A CN112599266 A CN 112599266A CN 202011329810 A CN202011329810 A CN 202011329810A CN 112599266 A CN112599266 A CN 112599266A
Authority
CN
China
Prior art keywords
spent fuel
fuel storage
plate
support plate
barrel
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
Application number
CN202011329810.3A
Other languages
Chinese (zh)
Inventor
祁杰
秦玮
刘慧芳
张洪军
谢亮
唐兴贵
张耀春
沈艳祥
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
China Nuclear Power Engineering Co Ltd
Original Assignee
China Nuclear Power Engineering Co Ltd
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by China Nuclear Power Engineering Co Ltd filed Critical China Nuclear Power Engineering Co Ltd
Priority to CN202011329810.3A priority Critical patent/CN112599266A/en
Publication of CN112599266A publication Critical patent/CN112599266A/en
Pending legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02Details of handling arrangements
    • G21C19/06Magazines for holding fuel elements or control elements
    • G21C19/07Storage racks; Storage pools
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C19/00Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/40Arrangements for preventing occurrence of critical conditions, e.g. during storage
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Fuel Cell (AREA)

Abstract

The invention discloses a spent fuel storage grillwork which comprises a main body and a fuel cell; the fuel cells are arranged on the main body in an equal grid pitch; neutron poison materials are arranged on the side wall of the fuel cell; the fuel cell comprises a barrel and a cladding; the cladding is fixedly connected with the cylinder body; the neutron poison material is disposed between the cladding and the barrel. The invention has the beneficial effects that: according to the invention, the neutron poison material is attached to the side wall of the cylinder body, so that the domestic mature neutron poison material is adopted to replace the boron stainless steel pipe, and the cost is reduced. According to the invention, the sealed barrel cells which can be used for storing the damaged fuel assembly sealed barrel are embedded in the spent fuel storage grillwork, and the optimal distribution and arrangement relationship of the number of the spent fuel storage grillwork cells and the number of the sealed barrel storage cells is selected according to the requirements of the nuclear power station, so that the grillwork is uniform in type and matched with a unique tool, and the stable reliability of processing and manufacturing is improved.

Description

Spent fuel storage grillwork
Technical Field
The invention belongs to the field of nuclear industry, relates to a fuel storage or reactor fuel storage facility in a nuclear power station, and particularly relates to a spent fuel storage grillwork.
Background
The spent fuel storage grillwork is mainly used for storing spent fuel assemblies underwater in the nuclear power station, storing new fuel assemblies to be stacked before shutdown refueling and during refueling, and is one of important equipment for storing spent fuel in the nuclear power station. The spent fuel storage grillwork is equipment for storing spent fuel assemblies by a wet method, and the safe storage of the spent fuel assemblies is ensured without critical accidents and overheating accidents of the fuel assemblies. Neutron poison materials in the spent fuel storage grillwork ensure that the spent fuel assembly is in a subcritical state, boron-containing deionized water in the spent fuel pool takes away heat generated by decay of the assembly, and the spent fuel assembly can be isolated from the outside to prevent radiation from being caused to the outside.
At present, boron stainless steel tubes are used as neutron poison materials for the storage grillwork of the hexagonal fuel assembly suitable for the VVER unit, the boron content of the materials is low (the conventional content is 1.7 percent, and the maximum content is 2.2 percent), and the boron stainless steel tubes are all imported at present, so that the cost is high, and the use is limited. The boron stainless steel pipes can not be welded and are fixedly connected in a mode of adding pin shafts to the stainless steel connecting blocks, the stainless steel connecting blocks are fixedly welded with the upper supporting plate and the lower supporting plate, and meanwhile the connecting blocks are welded to form a whole.
There are different forms of cell distribution within a fuel storage grid and in addition to the need for separately providing a damaged fuel assembly containment drum storage grid for the storage of damaged fuel assemblies. Due to the diversity of the grid varieties, different tools and processes need to be matched aiming at different forms of grids in the machining process, and the stable and reliable machining process is not facilitated to be formed.
In view of the above, the present invention is particularly proposed.
Disclosure of Invention
Aiming at the defects in the prior art, the invention aims to provide the spent fuel storage grillwork, and the technical scheme can replace the boron stainless steel pipe which can only be imported with domestic mature neutron poison materials, so that the cost is reduced.
The technical scheme of the invention is as follows:
a spent fuel storage grillwork comprises a main body and fuel cells; the fuel cells are arranged on the main body in an equal grid pitch; neutron poison materials are arranged on the side wall of the fuel cell; the fuel cell comprises a barrel and a cladding; the cladding is fixedly connected with the cylinder body; the neutron poison material is disposed between the cladding and the barrel.
Further, the spent fuel storage grid as described above, the main body comprises a top support plate and a bottom support plate; and the top supporting plate and the bottom supporting plate are fixedly connected with the fuel small chamber.
Further, in the spent fuel storage grid, the cross section of the cylinder is hexagonal, and the bottom support plate is welded to four side surfaces of the cylinder; the four sides are two sets of opposing sides of a hexagon.
Furthermore, in the spent fuel storage grillwork, the top supporting plate is provided with holes matched with the fuel cells, and the upper ends of the holes are provided with chamfers; the cylinder part of the small fuel chamber is inserted into the hole; the top end of the cylinder body is connected with the inner corner of the hole in a welding mode.
Further, in the spent fuel storage grid, the neutron poison material is B4C strengthens aluminium base composite sheet of granule.
Further, in the above spent fuel storage lattice frame, the main body is further provided with sealed barrel cells.
Further, in the above spent fuel storage grid, the cells of the sealed barrel comprise the guide members and the positioning holes; the upper end of the opening of the top supporting plate is provided with a chamfer, and the lower end of the opening of the top supporting plate is provided with the guide piece so as to guide the sealing barrel; the positioning hole is arranged on the bottom supporting plate and used for inserting the bolt at the bottom of the sealing barrel to realize the positioning function.
Further, in the above spent fuel storage grid, the support plate further includes a middle support plate; the middle bearing plate is provided with a support hole to support the fuel cell and the sealing barrel of the sealing barrel cell.
Further, in the spent fuel storage grid, the top support plate, the middle support plate and the bottom support plate are connected through the support columns; a coaming is connected between the supporting columns; the support columns comprise an upper support column and a lower support column; and the parts of the upper support column and the lower support column, which are in contact with each other, are respectively provided with a round hole and a cylinder which are connected with each other.
Further, in the spent fuel storage grillwork, a plurality of sleeves are mounted at the bottom of the bottom support plate; the support comprises a supporting pipe, a horizontal plate and a rib plate; the supporting pipe and the rib plate are both connected with the horizontal plate; a water hole is formed on the supporting tube; the upper end of the supporting pipe is provided with an adjustable thread section, and the adjustable thread section is matched with the sleeve to realize the leveling of the main body.
Further, in the spent fuel storage grillwork, the bottom of the bottom support plate is provided with a plurality of threaded sleeves, and the support leg comprises an adjusting screw rod with external threads, a check ring and a cushion block; the adjusting screw is installed on the cushion block through a check ring and matched with the threaded sleeve.
The invention has the beneficial effects that:
(1) according to the invention, the neutron poison material is attached to the side wall of the cylinder body, so that the defect that the existing domestic mature neutron poison material cannot be welded is avoided, the domestic mature neutron poison material is adopted to replace the boron stainless steel pipe which can only be imported, and the cost is reduced.
(2) According to the invention, the sealed barrel cells which can be used for storing the damaged fuel assembly sealed barrel are embedded in the spent fuel storage grillwork, and the optimal distribution and arrangement relationship of the number of the spent fuel storage grillwork cells and the number of the sealed barrel storage cells is selected according to the requirements of the nuclear power station, so that the grillwork is uniform in type and matched with a unique tool, and the stable reliability of processing and manufacturing is improved.
Drawings
Fig. 1 is a schematic structural diagram of a spent fuel storage lattice according to the present invention.
Fig. 2 is a top view of fig. 1.
FIG. 3 is a schematic view of the structure of a fuel cell according to the present invention.
Fig. 4 is a schematic view of the structure of the lower support plate.
FIG. 5 is a schematic view of a portion of the lower support plate welded to the fuel cell.
Fig. 6-8 are schematic views of the welded portion of the top support plate.
Fig. 9 is a schematic diagram of the structure of the sealed barrel chamber.
Fig. 10 is a schematic view showing the connection of the upper support column and the lower support column.
Figure 11 is a schematic view of a stent support structure of the grid of the present invention.
Figure 12 is a schematic view of a leg support structure of the grid of the present invention.
Fig. 13 is a schematic structural view of the leg.
In the above drawings: 1. a top support plate; 2. a middle support plate; 3. a fuel cell; 4. sealing the small chamber of the barrel; 5. an upper support column; 6. a lower support column; 7. enclosing plates; 8. a bottom support plate; 9. a threaded sleeve; 10. a support tube; 11. a rib plate; 12. a horizontal plate; 13. adjusting the screw rod; 14. a retainer ring; 15. cushion blocks; 16. a sleeve; 301. a barrel; 302. a neutron poison material; 303. and (4) cladding.
Detailed Description
The invention is described in detail below with reference to the figures and examples.
As shown in fig. 1 and 2, the present invention discloses a spent fuel storage lattice, which comprises a main body and fuel cells 3; the fuel cells 3 are arranged on the main body at equal pitches; neutron poison material 302 is disposed on the side walls of the fuel cell 3.
As shown in fig. 9, the body comprises a top support plate 1 and a bottom support plate 8; the top support plate 1 and the bottom support plate 8 are both fixedly connected to the fuel cell 3.
The fuel cell 3 is of a sandwich sleeve structure, and the neutron poison material is fixed on a stainless steel pipe by adopting an open cladding through intermittent welding or plug welding. As shown in fig. 3, the fuel cell 3 includes a cylinder 301 and a shell 303; the cladding 303 is fixedly connected with the cylinder body 301; the neutron poison material 302 is disposed between the cladding 303 and the barrel 301.
The neutron poison material 302 is B4C reinforced particle aluminum-based composite board (boron aluminum board for short). In this embodiment, the cylinder 301 is a regular hexagonal stainless steel tube, the cladding 303 is an open type cladding, specifically, an open type stainless steel thin-wall shell made of a tire membrane, and an inner cavity is completely coated with a boron aluminum plate.
The length and the position of the boron aluminum plate need to cover the active section of the fuel assembly, the boron aluminum plate is fixed on 6 surfaces of the stainless steel pipe through the cladding 303 and is not connected with any item, the open cladding and the stainless steel pipe are directly connected in a welding mode, and the mode of hole plug welding of straight side sections of four sides of the cladding 303 or the mode of fillet welding of the four sides of the cladding 303 and the stainless steel pipe can be adopted.
Material aspect, neutron poison material B4The C reinforced particle aluminum-based composite boron aluminum plate has high boron surface density (which can reach more than 5 times of boron stainless steel with the same thickness and the density is only 1/3 of the boron surface density) and excellent comprehensive performance, and is the most effective neutron poison material at present. Because the spent fuel storage framework is underwater for a long time, the materials of other parts except the neutron poison material are basically ultra-low carbon austenitic stainless steel.
Structural aspect, neutron poison material B4The C reinforced particle aluminum-based composite board has poor weldability, so the C reinforced particle aluminum-based composite board is fixed in a cladding mode.
The cross section of the cylinder body 301 is hexagonal, and the bottom supporting plate 8 is welded with four side surfaces of the cylinder body 301 in consideration of process accessibility and reduction of welding amount; the four sides are two sets of opposing sides of a hexagon (as shown in fig. 4 and 5) based on the consideration that welding distortion affects the verticality of a normal cell.
The interlayer sleeves are regularly distributed on the bottom support plate 8 at equal grid intervals (the distance from the center to the center of the adjacent fuel small chambers) and are connected in a welding mode, and the bottom support plate 8 is provided with a water drainage hole at the center of each interlayer sleeve so as to enable water to enter the fuel small chambers 3 from the water drainage holes to cool the fuel assemblies. The value of the grid distance needs to ensure critical safety. The middle supporting plate 2 is provided with a plurality of hexagonal holes matched with the maximum section outline size of the interlayer sleeve, and the distance between every two adjacent hexagonal holes is the same as the grid distance, so that the interlayer sleeves are spaced from each other and the verticality requirement during installation can be ensured.
As shown in fig. 6-8, the top support plate 1 is provided with a hole (the hole is a hexagonal hole matched with the cross-sectional dimension of the stainless steel tube) matched with the fuel cell 3, and the upper end of the hole is provided with a chamfer; the cylinder 301 of the fuel cell 3 is partially inserted into the hole; the top end of the barrel 301 is connected with the inside corner of the hole by welding to enhance the strength of the whole framework. Meanwhile, the fillet weld and the chamfer angle on the upper part of the hexagonal hole form a guide cylinder, so that the structure is simplified and the function of guiding the fuel assembly can be realized. The welding line between the cylinder 301 and the top support plate 1 strengthens the overall strength of the grid, and is beneficial to meeting the mechanical and anti-seismic requirements of the grid under various working conditions.
As shown in fig. 1 and 2, a sealed barrel chamber 4 is also disposed on the body. The sealing barrel chamber 4 comprises a guide part and a positioning hole; the upper end of the opening of the top supporting plate 1 is provided with a chamfer, and the lower end of the opening is provided with the guide piece to guide the sealing barrel, so that the sealing barrel can be inserted conveniently; the positioning hole is arranged on the bottom supporting plate 8 for inserting the bottom plug pin of the sealing barrel to realize the positioning function.
As shown in fig. 9, the support plates further include a middle support plate 2; the middle support plate 2 is provided with support holes to support the fuel cell 3 and the sealed barrel of the sealed barrel cell 4. The openings of the middle support are similar to the openings of the top support, the size of the support holes is determined according to the maximum cross-sectional profile size of the corresponding sandwich sleeve or sealing barrel, and the openings of the top support plate 1 and the middle support plate need to be provided with a pairing gap. The function of the middle support plate 2 is to ensure the verticality of the fuel cells 3, the grid distance between the cells and the strength of the whole grid. Meanwhile, the middle support plate 2 can prevent the deformation of the sealing barrel due to the large height-diameter ratio of the sealing barrel during long-term storage.
As shown in fig. 1, 9 and 10, the top support plate 1, the middle support plate 2 and the bottom support plate 8 are connected by support columns; enclosing plates 7 are further connected between the supporting columns (four sides of the enclosing plates 7 are respectively welded with the supporting plates and the supporting columns); the support columns comprise an upper support column 5 and a lower support column 6; and the parts of the upper support column and the lower support column which are connected with each other are respectively provided with a round hole and a cylinder which are matched with each other. The fuel cells 3 are distributed on a bottom support plate 8, and the fuel cells 3 are separated from each other and connected with each other by a top support plate 1 and a middle support plate 2, and then form a metal storage cabin in the shape of a rectangular parallelepiped through upper and lower support columns and upper and lower enclosing plates. The structure is beneficial to the overall strength of the grillwork, so that the grillwork cannot deform under normal working conditions and earthquake working conditions or the fuel assembly is still in a subcritical, natural cooling and circulating cooling state after deformation.
As shown in fig. 11, a plurality of sleeves 16 are installed at the bottom of the bottom supporting plate 8, and the bracket comprises a supporting pipe 10, a horizontal plate 12 and a rib plate 11; the supporting pipe 10 and the rib plate 11 are both connected with the horizontal plate 12; a water hole is formed on the supporting tube; the upper end of the supporting pipe 10 is provided with an adjustable thread section which is matched with the sleeve 16 to realize the leveling of the main body, the grid is ensured to be horizontally positioned, and when the position of the sleeve 16 is overlapped with the drain hole of the bottom supporting plate 8, water flow can enter the fuel cell 3 through the opening on the supporting pipe 10. When the lattice frame is installed in the dead pool, firstly, the supporting pipe 10 is respectively welded with the dead pool embedded part, then the supporting pipe 10 is adjusted to be threaded to an elevation, and finally, the sleeve 16 is simultaneously inserted into the supporting pipe 10.
As shown in fig. 12 and 13, a plurality of screw sleeves 9 are mounted at the bottom of the bottom support plate 8, and the support legs comprise an adjusting screw 13 with external threads, a retainer ring 14 and a cushion block 15; the adjusting screw is arranged on the cushion block 15 through a retainer ring 14 and matched with the threaded sleeve 9. The external thread of the adjusting screw 13 is meshed with the internal thread of the threaded sleeve 9, the grid can be horizontally positioned by rotating the adjusting screw 13, each supporting leg can be uniformly stressed, and four small water drainage holes are additionally arranged at the position of the bottom supporting plate 8 where the supporting leg is positioned so as to allow water to flow into the fuel cell 3. When the grillage supported by the supporting legs is in place, no mechanical connection is formed between the grillage and the steel cladding of the spent pool, and the grillage only needs to be placed in the spent pool.
According to the invention, the neutron poison material 302 is attached to the side wall of the barrel 301, so that the defect that the existing domestic mature neutron poison material cannot be welded is avoided, the domestic mature neutron poison material is adopted to replace the boron stainless steel tube which can only be imported, and the cost is reduced. According to the invention, the sealed barrel cells 4 which can be used for storing the damaged fuel assembly sealed barrel are embedded in the spent fuel storage grillwork, and the optimal distribution and arrangement relationship of the number of spent fuel storage grillwork cells and the number of sealed barrel storage cells is selected according to the requirements of the nuclear power station, so that the grillwork is uniform in type and matched with a unique tool, and the stable reliability of processing and manufacturing is improved.
The spent fuel storage framework for the nuclear power station uses the boron aluminum plate as the neutron poison material, so that the localization requirement is met, and meanwhile, the boron aluminum plate has the advantages of high boron content, low cost and the like. The grid can store fuel assemblies and damaged fuel assembly sealing barrels, achieves two functions of the grid, and enables the processing technology to be stable and reliable. The invention provides two forms of grid support modes which can be selected for use according to the site conditions of the nuclear power station and related professional calculation results.
It will be apparent to those skilled in the art that various changes and modifications may be made in the present invention without departing from the spirit and scope of the invention. Thus, if such modifications and variations of the present invention fall within the scope of the claims of the present invention and their equivalents, the present invention is intended to include such modifications and variations.

Claims (11)

1. A spent fuel storage grillwork is characterized by comprising a main body and fuel cells; the fuel cells are arranged on the main body in an equal grid pitch; neutron poison materials are arranged on the side wall of the fuel cell; the fuel cell comprises a barrel and a cladding; the cladding is fixedly connected with the cylinder body; the neutron poison material is disposed between the cladding and the barrel.
2. The spent fuel storage lattice of claim 1, wherein the body comprises a top support plate and a bottom support plate; and the top supporting plate and the bottom supporting plate are fixedly connected with the fuel small chamber.
3. The spent fuel storage lattice according to claim 2, wherein the cylinder is hexagonal in cross section, and the bottom support plate is welded to four sides of the cylinder; the four sides are two sets of opposing sides of a hexagon.
4. The spent fuel storage lattice of claim 2, wherein the top support plate is provided with holes matching the fuel cells, the holes being chamfered at upper ends thereof; the cylinder part of the small fuel chamber is inserted into the hole; the top end of the cylinder body is connected with the inner corner of the hole in a welding mode.
5. The spent fuel storage lattice of claim 1, wherein: the neutron poison material is B4C strengthens aluminium base composite sheet of granule.
6. The spent fuel storage lattice of claim 2, wherein: a sealed barrel chamber is also disposed on the body.
7. The spent fuel storage lattice of claim 6, wherein: the small chamber of the sealing barrel comprises a guide part and a positioning hole; the upper end of the opening of the top supporting plate is provided with a chamfer, and the lower end of the opening of the top supporting plate is provided with the guide piece so as to guide the sealing barrel; the positioning hole is arranged on the bottom supporting plate and used for inserting the bolt at the bottom of the sealing barrel to realize the positioning function.
8. The spent fuel storage lattice of claim 7, wherein: the support plate further comprises a middle support plate; the middle bearing plate is provided with a support hole to support the fuel cell and the sealing barrel of the sealing barrel cell.
9. The spent fuel storage grid according to claim 7, wherein the top support plate, the middle support plate, and the bottom support plate are connected by support columns; a coaming is connected between the supporting columns; the support columns comprise an upper support column and a lower support column; and the parts of the upper support column and the lower support column which are connected with each other are respectively provided with a round hole and a cylinder which are matched with each other.
10. The spent fuel storage lattice of any one of claims 2 to 9, wherein a plurality of sleeves are mounted to the bottom of the bottom support plate; the support comprises a supporting pipe, a horizontal plate and a rib plate; the supporting pipe and the rib plate are both connected with the horizontal plate; a water hole is formed on the supporting tube; the upper end of the supporting pipe is provided with an adjustable thread section, and the adjustable thread section is matched with the sleeve to realize the leveling of the main body.
11. The spent fuel storage lattice of any one of claims 2 to 9, wherein a plurality of threaded sleeves are mounted at the bottom of the bottom support plate; the supporting leg comprises an adjusting screw rod with external threads, a check ring and a cushion block; the adjusting screw is installed on the cushion block through a check ring and matched with the threaded sleeve.
CN202011329810.3A 2020-11-24 2020-11-24 Spent fuel storage grillwork Pending CN112599266A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202011329810.3A CN112599266A (en) 2020-11-24 2020-11-24 Spent fuel storage grillwork

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202011329810.3A CN112599266A (en) 2020-11-24 2020-11-24 Spent fuel storage grillwork

Publications (1)

Publication Number Publication Date
CN112599266A true CN112599266A (en) 2021-04-02

Family

ID=75183680

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202011329810.3A Pending CN112599266A (en) 2020-11-24 2020-11-24 Spent fuel storage grillwork

Country Status (1)

Country Link
CN (1) CN112599266A (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113921159A (en) * 2021-10-14 2022-01-11 中国核电工程有限公司 Spent fuel storage and transportation hanging basket

Citations (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0120232A1 (en) * 1983-03-01 1984-10-03 Westinghouse Electric Corporation Storage of spent nuclear fuel
JP2000227494A (en) * 1999-02-03 2000-08-15 Mitsubishi Heavy Ind Ltd Spent-fuel storing rack and its manufacture
CN101783189A (en) * 2009-01-21 2010-07-21 中国核电工程有限公司 Spent fuel storage rack in pressurized water reactor nuclear power station
CN102005252A (en) * 2010-10-14 2011-04-06 中广核工程有限公司 Depleted fuel storage grillwork for pressurized water reactor nuclear power station
CN102479560A (en) * 2010-11-23 2012-05-30 大连创达技术交易市场有限公司 Spent fuel storage grillwork for nuclear power station
CN102723115A (en) * 2012-06-29 2012-10-10 中广核工程有限公司 Spent fuel storage grillage for nuclear power plant
CN102737741A (en) * 2012-07-12 2012-10-17 中广核工程有限公司 Spent fuel storage framework of nuclear power plant
CN103400616A (en) * 2013-08-12 2013-11-20 上海阿波罗机械股份有限公司 Spent fuel rod storage grillwork module for nuclear power plant
JP2014071049A (en) * 2012-09-28 2014-04-21 Toshiba Corp Damaged fuel storage rack
JP2014089166A (en) * 2012-10-31 2014-05-15 Nippon Light Metal Co Ltd Neutron absorber and manufacturing method of the same
JP2014119321A (en) * 2012-12-14 2014-06-30 Mitsubishi Heavy Ind Ltd Fuel storage rack and installation method of the same
CN105931687A (en) * 2016-06-14 2016-09-07 中国核电工程有限公司 Spent fuel storage cell
CN107316666A (en) * 2017-07-03 2017-11-03 北京科瑞华安科技有限公司 A kind of spent fuel storage rack
CN109243645A (en) * 2018-09-13 2019-01-18 中国核动力研究设计院 A kind of irradiated fuel assembly storage screen work
CN110534217A (en) * 2019-09-09 2019-12-03 中国船舶重工集团公司第七一九研究所 A kind of spent fuel storage rack with Yu Haiyang's nuclear power platform

Patent Citations (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0120232A1 (en) * 1983-03-01 1984-10-03 Westinghouse Electric Corporation Storage of spent nuclear fuel
JP2000227494A (en) * 1999-02-03 2000-08-15 Mitsubishi Heavy Ind Ltd Spent-fuel storing rack and its manufacture
CN101783189A (en) * 2009-01-21 2010-07-21 中国核电工程有限公司 Spent fuel storage rack in pressurized water reactor nuclear power station
CN102005252A (en) * 2010-10-14 2011-04-06 中广核工程有限公司 Depleted fuel storage grillwork for pressurized water reactor nuclear power station
CN102479560A (en) * 2010-11-23 2012-05-30 大连创达技术交易市场有限公司 Spent fuel storage grillwork for nuclear power station
CN102723115A (en) * 2012-06-29 2012-10-10 中广核工程有限公司 Spent fuel storage grillage for nuclear power plant
CN102737741A (en) * 2012-07-12 2012-10-17 中广核工程有限公司 Spent fuel storage framework of nuclear power plant
JP2014071049A (en) * 2012-09-28 2014-04-21 Toshiba Corp Damaged fuel storage rack
JP2014089166A (en) * 2012-10-31 2014-05-15 Nippon Light Metal Co Ltd Neutron absorber and manufacturing method of the same
JP2014119321A (en) * 2012-12-14 2014-06-30 Mitsubishi Heavy Ind Ltd Fuel storage rack and installation method of the same
CN103400616A (en) * 2013-08-12 2013-11-20 上海阿波罗机械股份有限公司 Spent fuel rod storage grillwork module for nuclear power plant
CN105931687A (en) * 2016-06-14 2016-09-07 中国核电工程有限公司 Spent fuel storage cell
CN107316666A (en) * 2017-07-03 2017-11-03 北京科瑞华安科技有限公司 A kind of spent fuel storage rack
CN109243645A (en) * 2018-09-13 2019-01-18 中国核动力研究设计院 A kind of irradiated fuel assembly storage screen work
CN110534217A (en) * 2019-09-09 2019-12-03 中国船舶重工集团公司第七一九研究所 A kind of spent fuel storage rack with Yu Haiyang's nuclear power platform

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113921159A (en) * 2021-10-14 2022-01-11 中国核电工程有限公司 Spent fuel storage and transportation hanging basket
CN113921159B (en) * 2021-10-14 2023-12-22 中国核电工程有限公司 Spent fuel storage and transportation hanging basket

Similar Documents

Publication Publication Date Title
US4749544A (en) Thin walled channel
CN101783189B (en) Spent fuel storage rack in pressurized water reactor nuclear power station
CN102005252B (en) Depleted fuel storage grillwork for pressurized water reactor nuclear power station
RU2583324C1 (en) Horizontal steam generator for reactor plant with water-cooled power reactor and reactor plant with said steam generator
CN112599266A (en) Spent fuel storage grillwork
CN102479560A (en) Spent fuel storage grillwork for nuclear power station
JPH02122299A (en) Manufacture of neutron absorbing member of control rod by use of tube with square cross-section and double laser welding
CN110415853A (en) Reprocessing plant irradiated fuel assembly stores and transports hanging basket
CN111710450A (en) Manufacturing process of spent fuel storage grillwork
CN103280246B (en) A kind of liquid heavy metal cooled reactor fuel element
CN109243645B (en) Spent fuel assembly storage grillwork
CN102332314B (en) Water-cooling wall
JPH05223980A (en) Tube type heat exchanger
CN112466500A (en) Spent fuel storage tank transport container for nuclear power station
CN111477358A (en) Strip grid cell combined positioning grid
RU2387032C1 (en) Cover for arranging and storing waste fuel assemblies of reactors vver-1000
CN108364699B (en) Reactor pressure vessel for metal coolant fast reactor
JP4227693B2 (en) Method for producing spent fuel storage rack
CN201859662U (en) Spent fuel storage framework for pressurized-water reactor nuclear power station
RU2331943C1 (en) Hood for placement and storage of spent fuel assemblies of pwr 1000-type reactors
CN212874068U (en) Strip grid cell combined positioning grid
USRE34246E (en) Thin walled channel
CN110853770B (en) Single-flow supercritical water-cooled reactor based on regular hexagonal fuel assembly
RU182068U1 (en) FUEL ASSEMBLY OF A NUCLEAR REACTOR ON FAST NEUTRONS WITH A LIQUID METAL HEATER
JP5951359B2 (en) Fuel storage facility

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