CN102117668B - Reactor core unloading tool - Google Patents

Reactor core unloading tool Download PDF

Info

Publication number
CN102117668B
CN102117668B CN200910216999.2A CN200910216999A CN102117668B CN 102117668 B CN102117668 B CN 102117668B CN 200910216999 A CN200910216999 A CN 200910216999A CN 102117668 B CN102117668 B CN 102117668B
Authority
CN
China
Prior art keywords
reactor core
assembly
inner tube
plate
outer tube
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.)
Active
Application number
CN200910216999.2A
Other languages
Chinese (zh)
Other versions
CN102117668A (en
Inventor
李文钰
罗文广
李劲松
陈启兵
闵照地
李成业
王立德
唐坤林
张强
黄仁忠
沈跃
陈志雄
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.)
Nuclear Power Institute of China
Original Assignee
Nuclear Power Institute of China
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 Nuclear Power Institute of China filed Critical Nuclear Power Institute of China
Priority to CN200910216999.2A priority Critical patent/CN102117668B/en
Publication of CN102117668A publication Critical patent/CN102117668A/en
Application granted granted Critical
Publication of CN102117668B publication Critical patent/CN102117668B/en
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • 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

  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

The invention belongs to an unloading tool and particularly relates to a reactor core unloading tool for a nuclear reactor. The reactor core unloading tool comprises a rotation control assembly, a transmission pair assembly, a gripper assembly and a baseplate. The rotation control assembly rotates to drive the transmission pair assembly to move vertically to ensure that the gripper assembly connected with the transmission pair assembly moves horizontally in the baseplate, and a sliding plate of the gripper assembly tightens a reactor core assembly inside a baseplate notch, thus the entire tool is lifted to enable a lower tube seat of the reactor core assembly to separate from a grid plate so that the purpose of successfully unloading a reactor core is achieved. The reactor core unloading tool provided by the invention can guarantee the structural completeness of the assemblies by gripping the lower tube seat of a fuel assembly without damaging a fuel core section.

Description

Reactor core unloading tool
Technical field
The invention belongs to a kind of discharging instrument, be specifically related to a kind of reactor core unloading tool for nuclear reactor.
Background technology
Reactor fuel assembly upper and lower is connector, goes up base and bottom nozzle, middle part is core material, while utilizing instrument to capture reactor fuel assembly, forbids to capture middle part core material section.Reactor fuel assembly is that reactor fuel assembly bottom nozzle coordinates with Turbogrid plates at reactor in-core modes of emplacement, generally adopts clearance fit.Conventionally with gripping tool, capture the upper base of reactor fuel assembly, generally by less power, can make reactor fuel assembly and Turbogrid plates depart from.But for accidental cause, as due to corrosion or other mechanically deforms, to make fuel assembly and Turbogrid plates be interference fit, need very large pulling force just can make assembly and Turbogrid plates depart from, use the method for base on existing instrument and crawl reactor fuel assembly thereof cannot make fuel assembly separated with Turbogrid plates, and may damage fuel core segment, cannot Assurance component structural integrity.
The instrument on the top of the crawl reactor fuel assembly using is at present hook structure, all for capturing base on fuel assembly, this instrument is applicable for the operation of conventional assembly discrepancy reactor core, but while existing the fuel assembly of interference fit to operate to fuel assembly and Turbogrid plates, there is very big risk, because its size and structure are difficult to accurately control the firmly size being applied on fuel assembly, thereby when unloading fuel assembly, very easily destroy fuel core segment, nuclear fuel occurs and reveal.
Summary of the invention
Technical matters to be solved by this invention is, provide a kind of effectively, the operation tool of standard, can take out safely the assembly of keeping somewhere in heap in-core.
The technical solution adopted in the present invention is:
A reactor core unloading tool, comprises rotation Control Component, transmission assembly, grappling fixture assembly and base plate; Described rotation Control Component comprises screw rod, nut and bearing; Described nut is tubular, is connected with screw rod; Transmission assembly comprises outer tube and inner tube, and described outer tube is connected with nut lower end by bearing, and inner tube is connected with screw rod, and inner tube is positioned at outer tube, has chute on outer tube, has the spline pin being connected with inner tube in chute; Grappling fixture assembly comprises connecting rod, pricker and slide plate, and the inner tube of one end of connecting rod and transmission assembly is connected, the other end is connected with slide plate, and the horizontal direction of slide plate one side is provided with pricker; Base plate is rectangular flat plate, and base plate is inserted in the bottom of outer tube, and the middle part, a side of base plate has the breach matching with size of components, the middle part hollow out of base plate, and inner side is provided with base plate chute, in base plate chute, is provided with slide plate; Two arms of rotation Control Component, transmission assembly and each two composition instruments of grappling fixture assembly, have H type locating support at the middle part of two arm outer tubes.
A kind of reactor core unloading tool as above, is characterized in: described outer tube is connected by coupling sleeve with nut, and outside, outer tube upper end is connected with coupling sleeve lower end, and coupling sleeve upper end is connected with nut by bearing.
A kind of reactor core unloading tool as above, is characterized in: the inner tube in described transmission assembly is welded on screw rod lower end in rotation Control Component, and material is 0Cr18Ni9; Outer tube adopts the cold drawn stainless-steel tube of high precision to be made.
A kind of reactor core unloading tool as above, is characterized in: the inner tube locating sleeve of restricted inner tube radial motion between the outside on described inner tube top and outer tube inner side.
A kind of reactor core unloading tool as above, is characterized in: the connecting rod of described grappling fixture assembly is connected with the inner tube of transmission assembly by inner tube end plug, and described inner tube plug welding is connected on inner tube lower end, and has the bolt arrangement being connected with connecting rod; The outer tube of described transmission assembly is connected with base plate by outer pipe connected pipe.
A kind of reactor core unloading tool as above, its unique point is: described pricker is bullet shaped structure, and top is cone, and bottom is right cylinder, adopts martensitic stain less steel 3Cr13 to make, and by helicitic texture, is connected with slide plate.
A kind of reactor core unloading tool as above, its unique point is: described H type locating support comprises the vertical tube at middle part horizontal tube and two ends, left and right, between each pipe, by welding, make, and with lock-screw, locating support is fixed on outer tube, usage quantity is more than 2.
A kind of reactor core unloading tool as above, its unique point is: described base plate comprises upper plate, middle plate and lower plate, and three links together with screw, adopts pin location; Middle plate is less than upper plate and lower plate in the size at base plate runner position place.
A kind of reactor core unloading tool as above, its unique point is: described outer tube chute place is provided with scale, the degree that indication pricker thrusts fuel assembly.
A kind of reactor core unloading tool as above, is characterized in: on screw rod, be provided with and be convenient to the hanger that is connected with hoist lifting hook.
The invention has the beneficial effects as follows:
1. reactor core unloading tool provided by the invention, by capturing fuel assembly bottom nozzle, can not damage fuel core segment, possible Assurance component structural integrity.
2. the present invention drives inner tube by lead screw pair, inner tube moves downward, and makes lower link descending, pushes away before forcing slide plate, make the pricker that is arranged on slide plate head thrust assembly and Turbogrid plates binding site, finally make instrument and module composition one, then by hoisting tool, assembly is proposed, at it, be pulled out after Turbogrid plates, reverse rotation screw thread, make pricker exit assembly, remove instrument, then with manual component operation tool, it is carried out to subsequent operation.
3. acting as of spline pin: the one, guarantee when nut rotates, screw rod can not followed rotation together, and upper and lower rectilinear motion only occurs between screw rod and outer tube, and the 2nd, by observing the relative position of spline pin and outer tube, determine that pricker thrusts the degree of fuel assembly.
4. nut forms an integral body by bearing and coupling sleeve, whole assembly and outer tube link together by coupling bolt, have farthest reduced the friction force between nut and adapter sleeve, and then guarantee screw position self-locking, with nut, do not rotate, only produce vertical movement.
5. between nut and coupling sleeve, bearing is installed, therefore can effectively guarantee that without under External Force Acting, pricker can not detach assembly, has locking function.
6. on device screw rod, be provided with two hangers, by suspender belt, be connected with hoist lifting hook, by crane, carry out hoist tool.
7. the structure forming by inner tube end plug, connecting rod and slide plate, makes pricker thrust power much larger than the downward vertical of inner tube, has the effect of amplification power.
Accompanying drawing explanation
Fig. 1 is reactor core unloading tool structural representation;
Fig. 2 is that rotation is controlled and transmission components enlarged diagram;
Fig. 3 is transmission assembly, grappling fixture assembly and bottom parts schematic diagram;
Fig. 4 is the vertical view of reactor core unloading tool;
Fig. 5 is the slide plate schematic diagram of grappling fixture assembly;
Fig. 6 is the upper plate schematic diagram of base plate;
Fig. 7 is the middle plate schematic diagram of base plate;
Fig. 8 is the lower plate schematic diagram of base plate;
In figure: 101. rotation Control Components, 102. transmission assemblies, 103. grappling fixture assemblies, 104. base plate, 105. locating support, 201. hanger, 202. handle, 203. screw rod, 204. nut, 205. bearing, 206. bearing (ball) cover, 207. coupling sleeve, 208. inner tube locating sleeves, 209. outer tube, 210. inner tube, 211. spline pins, 212. chute, 301. inner tube end plugs, 302. outer pipe connected pipes, 303. pitman pin, 304. connecting rod, 305. slide plate engaging lugs, 306. pricker, 307. slide plate, 308. slide plate bearing pins, 309. upper plate, plate in 310., 311. lower plate, 401. base plate chutes.
Embodiment
Below in conjunction with drawings and Examples, a kind of reactor core unloading tool of the present invention is introduced:
As shown in Figure 1, a kind of reactor core unloading tool, comprises rotation Control Component 101, transmission assembly 102, grappling fixture assembly 103 and base plate 104.
As shown in Figure 2, rotation Control Component 101 comprises hanger 201, handle 202, screw rod 203, nut 204, bearing 205, bearing (ball) cover 206 and coupling sleeve 207.Handle 202 is connected with nut 204; The cylinder that nut 204 is hollow, can be cylinder, prismatic etc., and the diameter of bore of top hollow is less than the diameter of bore of bottom, and upper inner is threaded; Screw rod 203 runs through the hollow space of nut 204, and first half outside is threaded, by screw thread and nut 204 engagements; Utilize manpower or mechanical force swing handle can drive nut 204 rotations, nut 204 makes screw rod 203 promote or decline by screw thread; Nut 204 lower inside form an integral body by bearing 205, bearing (ball) cover 206 with coupling sleeve 207, and described coupling sleeve 207 is hollow, and top diameter of bore is less, and inside is equipped with screw rod 203; Coupling sleeve 207 bottom diameter of bores are greater than top, and in bottom, vacancy is except being equipped with screw rod 203, and screw rod 203 outsides are followed successively by inner tube locating sleeve and the outer tube of transmission assembly 102.Screw rod 203 upper ends are provided with for connecting the threaded hole of hanger 201; Connect the allocation and transportation that hanger 201 can be used for device.Described bearing (ball) cover 206 is used for fixing bearing 205.
As shown in Figure 2,3, transmission assembly 102 is positioned at rotation Control Component 101 lower ends, comprises inner tube locating sleeve 208, outer tube 209, inner tube 210, inner tube end plug 301 and outer pipe connected pipe 302;
Inner tube 208 is welded on screw rod 203 lower ends in rotation Control Component 101, and material is 0Cr18Ni9; Inner tube 208 overcoats have outer tube 209, together with outer tube 209 is bolted with the coupling sleeve 207 of rotation in Control Component 101, farthest reduced the friction force of 204, coupling sleeve 207 and nut, outer tube 209 adopts the cold drawn stainless-steel tube of high precision of Φ 45mm * 3.5mm to be made, on outer tube 209, having width is 6mm, length is the chute 212 of 100mm, has the spline pin 211 being connected with inner tube 210 in chute 212, and spline pin 211 is of a size of the pole of Φ 5mm * 60mm; Spline pin 211 has guaranteed that with chute 212 structures the screw rod 203 being connected with inner tube 210 can not rotate, and upper and lower rectilinear motion only occurs when nut 204 rotates.Described outer tube chute (212) locates to be provided with scale.
In order to limit inner tube 210, in outer tube 209, move radially distance, inner tube 210 upper outside have inner tube locating sleeve 208; Inner tube locating sleeve 208 and outer tube 209 weld together, and the interior hole dimension of inner tube locating sleeve 208 is greater than inner tube 210 external diameter 1mm; Inner tube 210 lower ends are also welded with inner tube end plug 301, have the pitman pin 303 that plays connection function with the connecting rod 304 of grappling fixture assembly 103 on inner tube end plug 301; Outer tube 209 bottom outside have outer pipe connected pipe 302, and outer pipe connected pipe 302 inserts base plates 104, and are connected for bolt with base plate 104.
The up and down rectilinear motion of inner tube 210 in transmission assembly 102 in outer tube 209, will drive grappling fixture assembly 103 in the interior horizontal gliding motility of bottom deck assembly 104.
As shown in Figure 3, described grappling fixture assembly 103 comprises pitman pin 303, connecting rod 304, slide plate engaging lug 305, pricker 306, slide plate 307 and slide plate bearing pin 308; The inner tube end plug 301 of one end of connecting rod 304 and transmission assembly 102 links together by pitman pin 303, and the other end is connected with slide plate 307 by slide plate engaging lug 305, slide plate bearing pin 308; As shown in Figure 4,5, slide plate 307 is the corrosion resistant plate of a rectangular parallelepiped, in the chute of bottom deck assembly 104 madial walls, slides; The horizontal direction of the side that slide plate 307 contacts with fuel assembly is equidistantly provided with 3 prickers 306; Described pricker is bullet shaped structure, and top is cone, and bottom is right cylinder, and pricker 306 adopts martensitic stain less steel 3Cr13 to make, and by helicitic texture, is connected with slide plate 307.
Each two groups of rotation Control Component, transmission assembly and grappling fixture assemblies, form two arms of reactor core unloading tool, is the rigidity that makes two arms fix and guarantee whole device, has H type locating support 105, as shown in Figure 1 at the middle part of outer tube; Described H type locating support comprises the vertical tube Φ 45mm * 3.5mm at middle part horizontal tube Φ 57mm * 10mm and two ends, left and right, between each pipe, by being welded to connect, and with lock-screw, locating support is fixed on outer tube 209.Can be by requirement of strength and decision fixed position, installation site, usage quantity should be more than 2 or 2.
Base plate 104 plays the effect of supporting whole tool of unloading and location reactor fuel assembly, can be divided into upper plate 309, middle plate 310 and lower plate 311, and three links together with socket head cap screw.Base plate 104 is inserted by outer pipe connected pipe 302 in the bottom of outer tube 209, and links together with the bolt of base plate 104 by back-off.As shown in Figure 4, middle part, side of base plate has the breach matching with size of components, when guaranteeing to capture, can make the chuck of device just in assembly and Turbogrid plates junction.
As shown in Figure 4, the base plate chute 401 sliding in order to form grappling fixture assembly 103 middle slide plates 307, as shown in Fig. 6,7,8, middle plate runner position place size is less than upper plate and lower plate 6mm, when 3 laminates link together, just formed the base plate chute 401 that slide plate slides.Base plate adopts folded spelling of 3 layers of thick corrosion resistant plate of 10mm to form.
During use, this device is put into reactor core, base plate 104 is contacted with reactor lattice plate, adjustment means gap position, make reactor fuel assembly just in time in the breach in instrument, by handle 202 rotating nuts 204, owing to there being the restriction of spline pin 211, make rotatablely moving of nut 204 be converted to the vertical movement of screw rod 203, the vertical movement of screw rod 203 is delivered on inner tube end plug 301 by connecting superincumbent inner tube 210, by connecting rod 304, vertical movement is converted to slide plate 307 by upper plate 309, middle plate 310, tangential movement in the base plate chute 401 that lower plate 311 forms, continue rotating nut 204, force the pricker 306 that is arranged on slide plate 307 upper ends to thrust fuel assembly bottom nozzle.Now, tool of unloading and reactor fuel assembly connect into an integral body by pricker 306, owing between nut 204 and coupling sleeve 207, bearing 205 being installed, therefore can effectively guarantee without under External Force Acting, pricker 306 can not detach assembly, has locking function.Again whole device is passed through to hanger 201, with strip suspension, on the hook of crane, assembly and instrument are all up carried, finally make assembly depart from Turbogrid plates, reach and can go out smoothly the object of heap.

Claims (10)

1. a reactor core unloading tool, comprises rotation Control Component (101), transmission assembly (102), grappling fixture assembly (103) and base plate (104); Described rotation Control Component (101) comprises screw rod (203), nut (204) and bearing (205); Described nut (204) is tubular, is connected with screw rod (203); Transmission assembly (102) comprises outer tube (209) and inner tube (210), described outer tube (209) is connected with nut (204) lower end by bearing (205), inner tube (210) is connected with screw rod (203), inner tube (210) is positioned at outer tube (209), it is characterized in that: on the outer tube (209) in transmission assembly (102), have chute (212), in chute (212), have the spline pin (211) being connected with inner tube (210); Grappling fixture assembly (103) comprises connecting rod (304), pricker (305) and slide plate (306); The inner tube (210) of one end of connecting rod (304) and transmission assembly (102) is connected, and the other end is connected with slide plate (306); The horizontal direction of slide plate (306) one sides is provided with pricker (305); Base plate (104) is rectangular flat plate, base plate (104) is inserted in the bottom of outer tube (209), the middle part, a side of base plate (104) has the breach matching with size of components, the middle part hollow out of base plate (104), inner side is provided with base plate chute (401), is provided with slide plate (306) in base plate chute (401); Two arms of rotation Control Component (101), transmission assembly (102) and each two composition instruments of grappling fixture assembly (103), have H type locating support (105) at the middle part of two arm outer tubes (206).
2. a kind of reactor core unloading tool according to claim 1, it is characterized in that: described outer tube (209) is connected by coupling sleeve (207) with nut (204), outside, outer tube (209) upper end is connected with coupling sleeve (207) lower end, and coupling sleeve (207) upper end is connected with nut (204) by bearing (205).
3. a kind of reactor core unloading tool according to claim 1, is characterized in that: the inner tube (210) in described transmission assembly (102) is welded on screw rod (203) lower end in rotation Control Component (101), and material is 0Cr18Ni9; Outer tube (209) adopts the cold drawn stainless-steel tube of high precision to be made.
4. a kind of reactor core unloading tool according to claim 1, is characterized in that: the inner tube locating sleeve (208) of restricted inner tube (210) radial motion between the outside on described inner tube (210) top and outer tube (209) inner side.
5. a kind of reactor core unloading tool according to claim 1, it is characterized in that: the connecting rod (304) of described grappling fixture assembly (103) is connected with the inner tube (210) of transmission assembly (102) by inner tube end plug (301), described inner tube end plug (301) is welded on inner tube (210) lower end, and has the bolt arrangement being connected with connecting rod (304); The outer tube (209) of described transmission assembly (102) is connected with base plate (104) by outer pipe connected pipe (302).
6. a kind of reactor core unloading tool according to claim 1, it is characterized in that: described pricker (306) is bullet shaped structure, and top is cone, and bottom is right cylinder, adopt martensitic stain less steel 3Cr13 to make, by helicitic texture, be connected with slide plate (307).
7. a kind of reactor core unloading tool according to claim 1, it is characterized in that: described H type locating support (105) comprises the vertical tube at middle part horizontal tube and two ends, left and right, between each pipe, by welding, make, and it is upper with lock-screw, locating support (105) to be fixed on to outer tube (209), usage quantity is more than 2.
8. a kind of reactor core unloading tool according to claim 1, is characterized in that: described base plate (104) comprises upper plate (309), middle plate (310) and lower plate (311), and three links together with screw, adopts pin location; The size of middle plate (310) in base plate chute (401) position is less than upper plate (309) and lower plate (311).
9. a kind of reactor core unloading tool according to claim 1, is characterized in that: described outer tube chute (212) locates to be provided with scale, the degree that indication pricker (306) thrusts fuel assembly.
10. a kind of reactor core unloading tool according to claim 1, is characterized in that: on screw rod (203), be provided with and be convenient to the hanger (201) that is connected with hoist lifting hook.
CN200910216999.2A 2009-12-31 2009-12-31 Reactor core unloading tool Active CN102117668B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN200910216999.2A CN102117668B (en) 2009-12-31 2009-12-31 Reactor core unloading tool

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN200910216999.2A CN102117668B (en) 2009-12-31 2009-12-31 Reactor core unloading tool

Publications (2)

Publication Number Publication Date
CN102117668A CN102117668A (en) 2011-07-06
CN102117668B true CN102117668B (en) 2014-08-27

Family

ID=44216384

Family Applications (1)

Application Number Title Priority Date Filing Date
CN200910216999.2A Active CN102117668B (en) 2009-12-31 2009-12-31 Reactor core unloading tool

Country Status (1)

Country Link
CN (1) CN102117668B (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106531233B (en) * 2016-12-29 2017-08-25 中国科学院合肥物质科学研究院 A kind of reactor fuel assemblies
CN106531232B (en) * 2016-12-29 2017-09-22 中科瑞华原子能源技术有限公司 A kind of fuel assembly that can be used for integration to reload
CN111554420B (en) * 2020-05-15 2023-02-28 中国核动力研究设计院 Nuclear power station tank filling pool protection device

Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB786486A (en) * 1954-05-11 1957-11-20 Atomic Energy Authority Uk Improvements in or relating to nut and screw mechanisms
GB1003244A (en) * 1962-10-04 1965-09-02 Commissariat Energie Atomique Handling device having a detachable gripper
CN86100680A (en) * 1985-01-25 1986-09-10 西屋电气公司 Head tube nozzle subassembly to nuclear fuel assembly carries out equipment and the method that pre-assembled is used
US4659537A (en) * 1982-11-16 1987-04-21 Framatone Et Cogema Apparatus for maintenance of nuclear fuel assemblies
US4728480A (en) * 1985-02-12 1988-03-01 Westinghouse Electric Corp. Apparatus and method for refurbishing a spectral shift mechanism for a nuclear reactor fuel assembly
CN101543987A (en) * 2009-04-21 2009-09-30 中国原子能科学研究院 Tool for taking and placing sleeve of spent fuel assembly inclined conveyor
CN201359859Y (en) * 2009-01-21 2009-12-09 中国核电工程有限公司 Long pole gripping apparatus

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB786486A (en) * 1954-05-11 1957-11-20 Atomic Energy Authority Uk Improvements in or relating to nut and screw mechanisms
GB1003244A (en) * 1962-10-04 1965-09-02 Commissariat Energie Atomique Handling device having a detachable gripper
US4659537A (en) * 1982-11-16 1987-04-21 Framatone Et Cogema Apparatus for maintenance of nuclear fuel assemblies
CN86100680A (en) * 1985-01-25 1986-09-10 西屋电气公司 Head tube nozzle subassembly to nuclear fuel assembly carries out equipment and the method that pre-assembled is used
US4728480A (en) * 1985-02-12 1988-03-01 Westinghouse Electric Corp. Apparatus and method for refurbishing a spectral shift mechanism for a nuclear reactor fuel assembly
CN201359859Y (en) * 2009-01-21 2009-12-09 中国核电工程有限公司 Long pole gripping apparatus
CN101543987A (en) * 2009-04-21 2009-09-30 中国原子能科学研究院 Tool for taking and placing sleeve of spent fuel assembly inclined conveyor

Also Published As

Publication number Publication date
CN102117668A (en) 2011-07-06

Similar Documents

Publication Publication Date Title
CN102117668B (en) Reactor core unloading tool
CN110744492B (en) Remote bolt dismantling and automatic grabbing tool and application method thereof
US9649724B2 (en) Charging device of a welding fixture of spacer grid
CN103077755B (en) Rod cluster grabbing tool
CN102515016A (en) Automatic gripper for storage barrel
CN109968275B (en) On-site dismounting process for upper reactor internals control rod guide cylinder
CN104690664B (en) Test fixture charging crane
CN101543987B (en) Tool for taking and placing sleeve of spent fuel assembly inclined conveyor
CN202307176U (en) Rod cluster grabbing tool
KR101705476B1 (en) Apparatus and method for installing reactor repairing device
KR100867031B1 (en) Refueling Machine Grapple
KR101295068B1 (en) Finger grip type heat pipe inspection light-weighted robot of steam generator
CN106555404B (en) Foundation pit fashioned iron inner support axle power self compensating system
CN206263873U (en) A kind of ejector pin instrument removed for upper-part in-reactor component control rod guide tubes and bundles
KR100873953B1 (en) Device for pulling welded plug installed in the damaged heat exchanger tubes in steam generator
CN112071458A (en) Fuel rod extraction device
CN203579470U (en) Text fixture assembling and disassembling mechanism
CN206128084U (en) Back shaft power automatic compensating device in foundation ditch shaped steel
RU2528398C1 (en) Device for lifting and transfer of used fuel rod arrays
CN203582268U (en) Clamp for unloading front-section column of steel structure on site
CN111477371A (en) Pressure vessel top cover and in-pile component guiding device and hoisting method
TW200525554A (en) Fuel assembly top nozzle repair sleeve and method for repairing a fuel assembly
CN204689169U (en) A kind of fuel manipulator crane telescopic shaft anchor fitting
CN210209269U (en) Gas pipeline welding machine with double-side clamping mechanism for environmental protection engineering
CN201380461Y (en) Tool for taking up and putting down sleeve of spent fuel assembly inclined conveyor

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
C14 Grant of patent or utility model
GR01 Patent grant