CN207558440U - A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument - Google Patents

A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument Download PDF

Info

Publication number
CN207558440U
CN207558440U CN201720328462.5U CN201720328462U CN207558440U CN 207558440 U CN207558440 U CN 207558440U CN 201720328462 U CN201720328462 U CN 201720328462U CN 207558440 U CN207558440 U CN 207558440U
Authority
CN
China
Prior art keywords
upper tube
tube socket
power plant
nuclear power
fuel assembly
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
CN201720328462.5U
Other languages
Chinese (zh)
Inventor
李雷
翁晨阳
奚梅英
邵长磊
黄然
刘建文
贺小明
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.)
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Original Assignee
Shanghai Nuclear Engineering Research and Design Institute 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 Shanghai Nuclear Engineering Research and Design Institute Co Ltd filed Critical Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Priority to CN201720328462.5U priority Critical patent/CN207558440U/en
Application granted granted Critical
Publication of CN207558440U publication Critical patent/CN207558440U/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

Abstract

The utility model provides a kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument, and spy includes upper tube socket analog board, and the upper tube socket analog board is vertically installed at by installing backing plate in support device;Dowel hole is provided on the upper tube socket analog board, the dowel hole is vertically set;Pass through support column structural support below the upper tube socket analog board.Vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument provided by the utility model, is installed in nuclear auxiliary building fuel transport channel, the function of tool is to carry out load test and performance test to fuel handling machine and its gripping apparatus before fuel handling.

Description

A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument
Technical field
The utility model is related to nuclear power plant's operation and maintenance, fuel assemblies to operate, and in particular to a kind of vertically-mounted pressure Water-water reactor nuclear power plant fuel assembly crawl test instrument.
Background technology
The fuel handling and plug-in part of PWR nuclear power plant, which are switched, waits relevant operations, is mainly captured by fuel manipulator crane or fuel A series of special operating tools of machine carry carry out.Since the mechanical precision of fuel assembly requires the features such as high, safety requirements is high, It needs before operation fuel assembly every time, crawl experiment is carried out to dedicated equipment and tool.
Utility model content
The utility model in view of the deficiencies of the prior art, proposes that a kind of vertically-mounted PWR nuclear power plant fuel assembly is grabbed Take test instrument.
The utility model provides a kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument, including upper Tube socket analog board, the upper tube socket analog board is by installing backing plate in support device;It is set on the upper tube socket analog board Dowel hole is equipped with, the dowel hole is vertically set;By supporting rod structure branch below the upper tube socket analog board Support.
Preferably, the installation backing plate is installed on the support structure by fastener.
Preferably, the tool is installed in nuclear auxiliary building fuel transport channel, and mounting means is is vertically arranged to water Basin side wall portion, the installation backing plate are welded with basin side wall steel linear.
Preferably, before fuel handling machine and fuel assembly special operating tool is used to carry out formal fuel handling, behaviour Make personnel and manipulate fuel handling machine and its gripping apparatus, after running to above this tool, transfer gripping apparatus, coordinated by the dowel hole It is oriented to, gripping apparatus is transferred to grappling fixture and stretches into the upper tube socket analog board, open and locks grappling fixture, to be carried accordingly Lotus is tested.
Compared with prior art, the utility model has the advantages that:
1st, vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument provided by the utility model, is installed on core In auxiliary plant fuel transport channel, the function of tool is to carry out load examination to fuel handling machine and its gripping apparatus before fuel handling It tests and performance test.
2nd, vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument provided by the utility model, has upper tube Seat simulation harden structure, can accurately simulated fuel assembly and gripping apparatus interface;Supporting structure with eight support column compositions;With vertical Mounting means is mounted on the steel linear in water basin side wall portion.
Description of the drawings
Fig. 1 meets the vertically-mounted PWR nuclear power plant fuel assembly crawl experiment work of the preferred embodiment in the utility model The structure type axonometric drawing of tool
Fig. 2 meets the detailed construction three-view diagram of the preferred embodiment in the utility model
Fig. 3 meets the applying working condition schematic diagram of the preferred embodiment in the utility model
Wherein:1- positioning pins control in Fig. 1;The upper tube socket analog boards of 2-;3- supports rod structure;4- fasteners;5- installation pads Plate;
11- gripping tools grappling fixture in Fig. 3;The upper tube socket analog boards of 12-;13- supports rod structure;14- installs backing plate;15- water Pond steel linear
Specific embodiment
Above-mentioned purpose, feature and advantage to enable the utility model are more obvious understandable, below in conjunction with the accompanying drawings and have Body embodiment is described in further detail the utility model.
As shown in Figs. 1-3, the present embodiment provides a kind of vertically-mounted PWR nuclear power plant fuel assembly crawl experiment works Tool, including upper tube socket analog board, the upper tube socket analog board is by installing backing plate in support device;The upper tube socket Dowel hole is provided on analog board, the dowel hole is vertically set;Pass through branch below the upper tube socket analog board Platen structural support.
Preferably, the installation backing plate is installed on the support structure by fastener.
Preferably, the tool is installed in nuclear auxiliary building fuel transport channel, and mounting means is is vertically arranged to water Basin side wall portion, the installation backing plate are welded with basin side wall steel linear.
Preferably, before fuel handling machine and fuel assembly special operating tool is used to carry out formal fuel handling, behaviour Make personnel and manipulate fuel handling machine and its gripping apparatus, after running to above this tool, transfer gripping apparatus, coordinated by the dowel hole It is oriented to, gripping apparatus is transferred to grappling fixture and stretches into the upper tube socket analog board, open and locks grappling fixture, to be carried accordingly Lotus is tested.
Compared with prior art, the present embodiment has the advantages that:
1st, vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument provided in this embodiment, it is auxiliary to be installed on core It helps in workshop fuel transport channel, the function of tool is to carry out load test to fuel handling machine and its gripping apparatus before fuel handling And performance test.
2nd, vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument provided in this embodiment, has upper tube socket Harden structure is simulated, it can accurately simulated fuel assembly and gripping apparatus interface;Supporting structure with eight support column compositions;To pacify vertically Dress mode is mounted on the steel linear in water basin side wall portion.
Each embodiment is described by the way of progressive in this specification, the highlights of each of the examples are with other The difference of embodiment, just to refer each other for identical similar portion between each embodiment.For system disclosed in embodiment For, due to corresponding to the methods disclosed in the examples, so description is fairly simple, related part is referring to method part illustration .
Those skilled in the art can realize described function to each specific application using distinct methods, but It is this realize it is not considered that beyond the scope of the utility model.
Obviously, it is new without departing from this practicality can to carry out utility model various modification and variations by those skilled in the art The spirit and scope of type.If in this way, these modifications and variations of the present invention belong to the utility model claims and its Within the scope of equivalent technologies, then the utility model is also intended to including these modification and variations.

Claims (3)

1. a kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument, which is characterized in that including upper tube socket mould Intend plate, the upper tube socket analog board is vertically installed at by installing backing plate in support device;It is set on the upper tube socket analog board There is dowel hole, the dowel hole is vertically set;Pass through support column structural support below the upper tube socket analog board.
2. vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument as described in claim 1, which is characterized in that The installation backing plate is installed on the support structure by fastener.
3. vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument as described in claim 1, which is characterized in that The tool is installed in nuclear auxiliary building fuel transport channel, and mounting means is described to be vertically arranged to water basin side wall portion Installation backing plate is welded with basin side wall steel linear.
CN201720328462.5U 2017-03-30 2017-03-30 A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument Active CN207558440U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201720328462.5U CN207558440U (en) 2017-03-30 2017-03-30 A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201720328462.5U CN207558440U (en) 2017-03-30 2017-03-30 A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument

Publications (1)

Publication Number Publication Date
CN207558440U true CN207558440U (en) 2018-06-29

Family

ID=62672216

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201720328462.5U Active CN207558440U (en) 2017-03-30 2017-03-30 A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument

Country Status (1)

Country Link
CN (1) CN207558440U (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106910538A (en) * 2017-03-30 2017-06-30 上海核工程研究设计院 A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106910538A (en) * 2017-03-30 2017-06-30 上海核工程研究设计院 A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument

Similar Documents

Publication Publication Date Title
CN106935296A (en) A kind of PWR nuclear power plant fuel assembly crawl test instrument being horizontally mounted
CN107830168A (en) A kind of pressurized tank for being used to test underwater connector performance
CN205679468U (en) A kind of anchor rod drawing test hydraulic support device
CN104949892A (en) Stray current, chloridion and bending fatigue coupling loading simulating device
CN101857067B (en) Special support tooling for installing translational hatch cover of bulk carrier and installation method thereof
CN207558440U (en) A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument
CN207558442U (en) A kind of PWR nuclear power plant fuel assembly crawl test instrument being horizontally mounted
CN204059597U (en) A kind of bolt sleeve device realizing combining structure shear connector stiffness variation
CN205132263U (en) Novel ball formula falls to manage ware
CN105719711A (en) Earthquake-resistant support structure for reactor internal lifting tools of pressurized water reactor nuclear power plants
CN112908502B (en) Spring plate type horizontal and vertical bidirectional excitation decoupling device
CN111811850B (en) Anchor rod cable system cooperative bearing performance testing device and method
CN106910538A (en) A kind of vertically-mounted PWR nuclear power plant fuel assembly crawl test instrument
JP5916371B2 (en) Underwater plate bending apparatus and underwater reracing method using the apparatus
CN203559351U (en) Suspended bridge overhauling workbench
CN206848039U (en) Modularization fatigue test place and corollary apparatus
CN207932927U (en) The not contour bearing steel truss structure of large span lifts synchronization-sliding TT&C system
CN107314932B (en) Modularized fatigue test field, matched device and fatigue test method
CN203247828U (en) Suspension beam placing device
CN107884004A (en) A kind of method of test connector submerged performance
CN205642746U (en) Part water pressure testing device
CN205218474U (en) Piston servomotor shifts out device
CN206208633U (en) Concrete impervious test block speed dismantling device
CN206436183U (en) A kind of elastic cylindrical pin handling instrument
CN210690259U (en) Static casting elbow water pressure detection workbench

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant
CP01 Change in the name or title of a patent holder

Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.

Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai

Patentee before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE

CP01 Change in the name or title of a patent holder