CN203465957U - Device for checking reactor pressure vessel of nuclear power station - Google Patents

Device for checking reactor pressure vessel of nuclear power station Download PDF

Info

Publication number
CN203465957U
CN203465957U CN201320585946.XU CN201320585946U CN203465957U CN 203465957 U CN203465957 U CN 203465957U CN 201320585946 U CN201320585946 U CN 201320585946U CN 203465957 U CN203465957 U CN 203465957U
Authority
CN
China
Prior art keywords
pressure vessel
reactor pressure
nuclear power
checking
power plant
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.)
Expired - Lifetime
Application number
CN201320585946.XU
Other languages
Chinese (zh)
Inventor
张志义
王俊涛
周文
聂勇
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.)
Research Institute of Nuclear Power Operation
China Nuclear Power Operation Technology Corp Ltd
Original Assignee
Research Institute of Nuclear Power Operation
China Nuclear Power Operation Technology Corp 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 Research Institute of Nuclear Power Operation, China Nuclear Power Operation Technology Corp Ltd filed Critical Research Institute of Nuclear Power Operation
Priority to CN201320585946.XU priority Critical patent/CN203465957U/en
Application granted granted Critical
Publication of CN203465957U publication Critical patent/CN203465957U/en
Priority to GB1604800.1A priority patent/GB2533735B/en
Priority to PCT/CN2014/078617 priority patent/WO2015039459A1/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

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 utility model belongs to the technical field of checking of a reactor pressure vessel of a nuclear power station, and particularly relates to a device for checking the reactor pressure vessel of the nuclear power station. The checking device comprises a stand column assembly (2) and multiple checking tool carrying platforms (3), wherein the multiple checking tool carrying platforms (3) are arranged on the stand column assembly (2) from top to bottom, and checking tools for checking the reactor pressure vessel of the nuclear power station are arranged on the multiple checking tool carrying platforms (3); each checking tool carrying platform (3) can move in an upper and down lifting manner and a plane rotation manner around the stand column assembly (2). The checking device has the advantages that the technical problem that a conventional checking device for the reactor pressure vessel is low in checking efficiency is solved; the multiple checking tools can be simultaneously used for checking multiple locations and multiple zones of the reactor pressure vessel, so that the checking efficiency is obviously improved, and the reactor occupying time is shortened.

Description

A kind of nuclear power plant reactor pressure vessel testing fixture
Technical field
The utility model belongs to nuclear power plant reactor pressure vessel and checks technical field, is specifically related to a kind of nuclear power plant reactor pressure vessel testing fixture.
Background technology
Nuclear reactor pressure container (reactor pressure vessel) is the closed container of settling nuclear reactor and bearing its huge operating pressure, also claim nuclear reactor pressure shell, it is the key equipment in pressurized-water reactor nuclear power plant, the feature such as have that manufacturing technology standard is high, difficulty is large and the cycle is long, and be non-exchange equipment, must guarantee that it is perfectly safe in more than the lifetime of 40 years at nuclear power station reliable.Reactor pressure vessel is fixed and is contained reactor core nuclear fuel assembly and in-pile component, the fission reaction of nuclear fuel is limited in the space of a sealing to be carried out, it and primary coolant circuit pipe form the pressure boundary of pressure coolant jointly, are to prevent one of second barrier that radiomaterial leaks.
In nuclear power station operational process, reactor pressure vessel is in the environment of high temperature, high pressure, high radiation.Increase along with working time, the metallicity of container material can reduce gradually, metal uncontinuity also can produce, so be extremely necessary pressure vessel to detect, to find in time defect risk wherein, can be processed as early as possible, thereby the safety of maintenance and guarantee nuclear power facility avoids occurring serious safe operation and nuclear leakage accident.
Nuclear reactor pressure container is after the operation of power station, and internal tank is high radioactivity region, and the pressure vessel of pressurized water reactor type is submerged under water, isolated nuclear radiation.The device that comprehensive above-mentioned situation needs the nuclear reactor pressure container of a set of enforcement of Remote under water to check, only have in the world at present minority core developed country to develop nuclear reactor pressure container testing fixture and implement reactor pressure vessel inspection, domestic nuclear power reactor pressure vessel inservice inspection technology is existed and blocks monopolization, and each enforcement inspection all needs to pay through the nose.My department, through inservice inspection technological accumulation for many years, designs a kind of nuclear power plant reactor pressure vessel testing fixture, and this testing fixture checks from pressure vessel internal implementation, checks that environment both can air, also can be under water.
Existing nuclear reactor pressure container testing fixture, can only check for the nuclear power heap type of specific dimensions, versatility is poor; In addition, each inspection only can be used a checking tool to check nuclear reactor pressure container position, and checking efficiency is low.
Utility model content
The utility model technical issues that need to address are: the each inspection of existing nuclear reactor pressure container testing fixture only can be used a checking tool to check nuclear reactor pressure container position, and checking efficiency is low.
The technical solution of the utility model is as described below:
A kind of nuclear power plant reactor pressure vessel testing fixture, comprise columns assemblies and checking tool carrying platform, columns assemblies arranges a plurality of checking tool carrying platforms that nuclear power plant reactor pressure vessel checking tool is installed from top to bottom, and each checking tool carrying platform can carry out oscilaltion campaign and plane rotatablely moves around columns assemblies.
As preferred version, nuclear power plant reactor pressure vessel testing fixture also comprises the lifting supporting component that is fixed on columns assemblies top, promote the vessel flange top that supporting component is installed on nuclear power plant reactor pressure vessel, its size can regulate according to vessel flange size.For example: described lifting supporting component can comprise some inverted "L" shaped brace rods, between every brace rod upper end and columns assemblies, by the adjustable cushion block of thickness, be connected, lower end fixes with the vessel flange of nuclear power plant reactor pressure vessel: the thickness of the cushion block being connected by adjusting brace rod upper end, can adjust the sectional dimension that some brace rod lower ends surround, itself and vessel flange size are matched.
The installation of nuclear power plant reactor pressure vessel testing fixture on pressure vessel fixedly mainly contains two kinds of modes: (1) is fixed on pressure container flange seam end face, brace rod bottom is provided with feather key, insertion keyway is inner, realize testing fixture and determine at axial, the circumferential positioning datum of pressure vessel, see Fig. 6 (b); (2) install and be placed on pressure container flange pore area face, brace rod, through nuclear power station top cover installation guide finger, falls to putting on flange face.Guide finger, at 0 °, is determined axial, circumferential benchmark with this, and brace rod and flange are installed and adopted the two-wheel pin automatic attaching of 90 ° of angles at flange and seam face simultaneously, between supporting leg and guide finger, by cylinder clamping mechanism, lock, and see Fig. 6 (a).
As further preferred version, described columns assemblies, outer wall is provided with a toothed rack vertically; Described checking tool carrying platform, comprises inner core and urceolus, and the two fixes by swing bearing; Described checking tool carrying platform inner core, be provided with lifting driving motor, lifting transmission gear and support guide wheel: the tooth bar of lifting transmission gear and columns assemblies matches, supporting under the support of guide wheel and the driving of lifting driving motor, realize checking tool carrying platform along the elevating movement of columns assemblies; Described checking tool carrying platform urceolus, along continuous straight runs is provided with a circle gear ring, and it drives urceolus to horizontally rotate motion under the driving of rotary drive motor that is installed on inner core; In addition, urceolus is also provided with a plurality of mounting holes, and a plurality of checking tools can be installed simultaneously.
In addition, described column and outer wall can also be provided with guide rail and groove vertically, and columns assemblies length is adjustable; Described checking tool carrying platform urceolus, upper edge, lower edge can respectively be evenly distributed with a circle mounting hole, form circumferential flange formula datum clamp face.
The beneficial effects of the utility model are:
(1) nuclear power plant reactor pressure vessel testing fixture of the present utility model, can use a plurality of checking tools to carry out the many inspection areas of multiposition to nuclear reactor pressure container simultaneously and check, has significantly improved checking efficiency, has shortened and account for the heap time;
(2) nuclear power plant reactor pressure vessel testing fixture of the present utility model, when certain checking tool carrying platform breaks down, other platforms can complementaryly be implemented to check, improve the reliability of testing fixture;
(3) nuclear power plant reactor pressure vessel testing fixture of the present utility model, by regulating pad thickness to make to promote the vessel flange that supporting component can mate different size, versatility be improved significantly;
(4) nuclear power plant reactor pressure vessel testing fixture of the present utility model, it is inner that checking tool carrying platform arrives pressure vessel cylinder along columns assemblies, be not subject to the steel wire rope type lifting generally adopting in prior art, the restriction of telescopic sleeve pipe type sucking lifting, realize a plurality of checking tool carrying platforms in the inner differing heights areal distribution of pressure vessel, realize multiposition and check simultaneously;
(5) nuclear power plant reactor pressure vessel testing fixture of the present utility model, checking tool carrying platform urceolus is provided with a plurality of mounting holes, and a plurality of checking tools can be installed simultaneously;
(6) testing fixture utilizes the seam of pressure container flange face, the positioning datum checking as pressure vessel, because pressure container flange seam is machine work face, machining precision is high, realize pressure vessel inspection circumferentially, the determining fast of axial location benchmark, accurately.
Accompanying drawing explanation
Fig. 1 is the sectional view of the utility model nuclear power plant reactor pressure vessel testing fixture;
Fig. 2 is the vertical view of the utility model nuclear power plant reactor pressure vessel testing fixture;
Fig. 3 (a) and (b), (c), (d), (e), (f) are for being provided with the checking tool carrying platform schematic diagram of different checking tools;
Fig. 4 is for promoting supporting component structural representation;
Fig. 5 (a) is upright post component structure schematic diagram;
Fig. 5 (b) is columns assemblies partial enlarged drawing;
Fig. 5 (c) is for establishing reeded columns assemblies sectional view.
Fig. 6 (a), 6(b1) be the lay schematic diagram of the utility model nuclear power plant reactor pressure vessel testing fixture at pressure container flange assembly;
Fig. 6 (b2) is 6(b1) vertical view;
Fig. 6 (b3) is 6(b1) partial enlarged drawing.
In figure, 1-promotes supporting component, 2-columns assemblies, 3-checking tool carrying platform, 4-cushion block, 5-tooth bar, 6-guide rail, 7-groove, 8-circumferential flange formula datum clamp face.
Embodiment
Below in conjunction with drawings and Examples, nuclear power plant reactor pressure vessel testing fixture of the present utility model is elaborated.
Nuclear power plant reactor pressure vessel testing fixture of the present utility model, comprises and promotes supporting component 1, columns assemblies 2 and checking tool carrying platform 3.Wherein, columns assemblies 2 arranges a plurality of checking tool carrying platforms 3 that nuclear power plant reactor pressure vessel checking tool is installed from top to bottom; Each checking tool carrying platform 3 can carry out oscilaltion campaign and plane rotatablely moves around columns assemblies 2; Promote supporting component 1 and be fixed on columns assemblies 2 tops, for technician, nuclear power plant reactor pressure vessel testing fixture is promoted to outside nuclear power plant reactor pressure vessel, carry out turnaround of unit and checking tool and change.
Described lifting supporting component 1, is installed on above the vessel flange of nuclear power plant reactor pressure vessel, and its size can regulate according to the vessel flange size of different size nuclear power heap type.In the present embodiment, described lifting supporting component 1 comprises some inverted "L" shaped brace rods, between every brace rod upper end and columns assemblies 2 assemblies, by the adjustable cushion block 4 of thickness, is connected, and the vessel flange of lower end and nuclear power plant reactor pressure vessel fixes.By regulating the thickness of the cushion block 4 that brace rod upper end connects, can adjust the sectional dimension that some brace rod lower ends surround, make its coupling vessel flange size, the nuclear power heap type realizing for different size checks, versatility significantly improves.
Described columns assemblies 2, outer wall is provided with a toothed rack 5 and some guide rails 6 vertically: tooth bar 5 carries out 3 elevating movements of checking tool carrying platform for the gear of matching check instrument carrying platform 3; Guide rail 6 is for limiting the radial motion of checking tool carrying platform 3 and rotating in a circumferential direction.In the present embodiment, the post that columns assemblies 2 is all provided with tooth bar 5 and guide rail 6 vertically by more piece outer wall is formed by connecting, so that adjust columns assemblies 2 length for the nuclear power plant reactor pressure vessel of different depth.As preferred version, described columns assemblies 2 can also be provided with vertically for placing the groove 7 of cable.
Described checking tool carrying platform 3, comprises inner core and urceolus, and the two fixes by swing bearing.Inner core is provided with lifting driving motor, lifting transmission gear and supports guide wheel: the tooth bar 5 of lifting transmission gear and columns assemblies 2 matches, supporting under the support of guide wheel and the driving of lifting driving motor, realize checking tool carrying platform 3 along the elevating movement of columns assemblies 2.Urceolus along continuous straight runs is provided with a circle gear ring, and it drives urceolus to horizontally rotate motion under the driving of rotary drive motor that is installed on inner core; In addition, urceolus is also provided with a plurality of mounting holes, and a plurality of checking tools can be installed simultaneously, scanning when realizing nuclear power plant reactor pressure container cylinder inwall.In the present embodiment, the upper edge of urceolus, lower edge are respectively evenly distributed with a circle mounting hole, form circumferential flange formula datum clamp face 8: the mount pad of different checking tools is arranged on the optional position of flange form datum clamp face circumferencial direction according to actual needs, make same checking tool carrying platform 3 both can a plurality of checking tools be installed according to position of mounting hole adjustment, realize a plurality of checking tools in same inspection area and be advanced into a plurality of adapters or implement weld seam scanning in a plurality of angles simultaneously, significantly improving checking efficiency; The parts of other structure can be arranged on flange form datum clamp face again, expand different testing fixtures, increase testing fixture and mount a little, realize subsequent upgrade transformation.
A plurality of checking tool carrying platforms 3 carry out the multiposition multizone inspections such as nozzle inspection region, upper shell inspection area, lower shell inspection area in nuclear power plant reactor pressure vessel, have improved checking efficiency, have shortened the heap time that accounts for; When certain checking tool carrying platform 3 breaks down, other platforms can complementaryly be implemented to check, improve the reliability of testing fixture.
The installation of nuclear power plant reactor pressure vessel testing fixture of the present utility model on pressure vessel fixedly mainly contains two kinds of modes: (1) is fixed on pressure container flange seam end face, brace rod bottom is provided with feather key, insertion keyway is inner, realize testing fixture and determine at axial, the circumferential positioning datum of pressure vessel, see Fig. 6 (b1)~Fig. 6 (b3); (2) install and be placed on pressure container flange pore area face, brace rod, through nuclear power station top cover installation guide finger, falls to putting on flange face.Guide finger, at 0 °, is determined axial, circumferential benchmark with this, and brace rod and flange are installed and adopted the two-wheel pin automatic attaching of 90 ° of angles at flange and seam face simultaneously, between supporting leg and guide finger, by cylinder clamping mechanism, lock, and see Fig. 6 (a).

Claims (7)

1. a nuclear power plant reactor pressure vessel testing fixture, comprise columns assemblies (2) and checking tool carrying platform (3), it is characterized in that: columns assemblies (2) arranges a plurality of checking tool carrying platforms (3) that nuclear power plant reactor pressure vessel checking tool is installed from top to bottom; Each checking tool carrying platform (3) can carry out oscilaltion campaign and plane rotatablely moves around columns assemblies (2).
2. nuclear power plant reactor pressure vessel testing fixture according to claim 1, it is characterized in that: nuclear power plant reactor pressure vessel testing fixture also comprises the lifting supporting component (1) that is fixed on columns assemblies (2) top, promote the vessel flange top that supporting component (1) is installed on nuclear power plant reactor pressure vessel, its size can regulate according to vessel flange size.
3. nuclear power plant reactor pressure vessel testing fixture according to claim 2, it is characterized in that: described lifting supporting component (1) comprises some inverted "L" shaped brace rods, between every brace rod upper end and columns assemblies (2) assembly, by the adjustable cushion block of thickness (4), be connected, lower end fixes with the vessel flange of nuclear power plant reactor pressure vessel: the thickness of the cushion block (4) being connected by adjusting brace rod upper end, can adjust the sectional dimension that some brace rod lower ends surround, itself and vessel flange size are matched.
4. nuclear power plant reactor pressure vessel testing fixture according to claim 1 and 2, is characterized in that:
Described columns assemblies (2), outer wall is provided with a toothed rack (5) vertically;
Described checking tool carrying platform (3), comprises inner core and urceolus, and the two fixes by swing bearing;
Described checking tool carrying platform (3) inner core, be provided with lifting driving motor, lifting transmission gear and support guide wheel: the tooth bar (5) of lifting transmission gear and columns assemblies (2) matches, supporting under the support of guide wheel and the driving of lifting driving motor, realize checking tool carrying platform (3) along the elevating movement of columns assemblies (2);
Described checking tool carrying platform (3) urceolus, along continuous straight runs is provided with a circle gear ring, and it drives urceolus to horizontally rotate motion under the driving of rotary drive motor that is installed on inner core; In addition, urceolus is also provided with a plurality of mounting holes, and a plurality of checking tools can be installed simultaneously.
5. nuclear power plant reactor pressure vessel testing fixture according to claim 4, is characterized in that: described column and outer wall are also provided with guide rail (6) and groove (7) vertically.
6. nuclear power plant reactor pressure vessel testing fixture according to claim 4, is characterized in that: described columns assemblies (2) can regulate length.
7. nuclear power plant reactor pressure vessel testing fixture according to claim 4, is characterized in that: described checking tool carrying platform (3) urceolus, upper edge, lower edge are respectively evenly distributed with a circle mounting hole, form circumferential flange formula datum clamp face (8).
CN201320585946.XU 2013-09-23 2013-09-23 Device for checking reactor pressure vessel of nuclear power station Expired - Lifetime CN203465957U (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
CN201320585946.XU CN203465957U (en) 2013-09-23 2013-09-23 Device for checking reactor pressure vessel of nuclear power station
GB1604800.1A GB2533735B (en) 2013-09-23 2014-05-28 Apparatus for inspecting a reactor pressure vessel of a nuclear power plant
PCT/CN2014/078617 WO2015039459A1 (en) 2013-09-23 2014-05-28 Device for checking reactor pressure vessel of nuclear power station

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201320585946.XU CN203465957U (en) 2013-09-23 2013-09-23 Device for checking reactor pressure vessel of nuclear power station

Publications (1)

Publication Number Publication Date
CN203465957U true CN203465957U (en) 2014-03-05

Family

ID=50178306

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201320585946.XU Expired - Lifetime CN203465957U (en) 2013-09-23 2013-09-23 Device for checking reactor pressure vessel of nuclear power station

Country Status (1)

Country Link
CN (1) CN203465957U (en)

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN103985424A (en) * 2014-05-29 2014-08-13 中广核检测技术有限公司 Nuclear reactor pressure vessel nondestructive detection robot and detection method thereof
CN104002306A (en) * 2014-05-13 2014-08-27 中国科学院深圳先进技术研究院 Telescopic mechanical arm
CN104015199A (en) * 2014-05-29 2014-09-03 中广核检测技术有限公司 Mechanical arm and detection robot based on mechanical arms
CN104464849A (en) * 2013-09-23 2015-03-25 核动力运行研究所 Device for checking reactor pressure vessel of nuclear power station
WO2015039459A1 (en) * 2013-09-23 2015-03-26 核动力运行研究所 Device for checking reactor pressure vessel of nuclear power station
CN105810275A (en) * 2014-12-30 2016-07-27 中核武汉核电运行技术股份有限公司 Purification system for reactor cavity of reactor
CN109979616A (en) * 2017-12-27 2019-07-05 核动力运行研究所 Open frame is independently unfolded in a kind of nuclear reactor pressure container
US11187527B2 (en) * 2019-10-07 2021-11-30 The Boeing Company Multi-probe non-destructive inspection system

Cited By (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2533735A (en) * 2013-09-23 2016-06-29 Res Inst Nuclear Power Operation Device for checking reactor pressure vessel of nuclear power station
GB2533735B (en) * 2013-09-23 2020-07-29 Res Inst Nuclear Power Operation Apparatus for inspecting a reactor pressure vessel of a nuclear power plant
CN104464849A (en) * 2013-09-23 2015-03-25 核动力运行研究所 Device for checking reactor pressure vessel of nuclear power station
WO2015039459A1 (en) * 2013-09-23 2015-03-26 核动力运行研究所 Device for checking reactor pressure vessel of nuclear power station
CN104002306A (en) * 2014-05-13 2014-08-27 中国科学院深圳先进技术研究院 Telescopic mechanical arm
CN104002306B (en) * 2014-05-13 2016-03-30 中国科学院深圳先进技术研究院 Telescopic magic hand
CN103985424A (en) * 2014-05-29 2014-08-13 中广核检测技术有限公司 Nuclear reactor pressure vessel nondestructive detection robot and detection method thereof
EP3151246B1 (en) 2014-05-29 2019-02-27 CGN Inspection Technology Company, Ltd. Nondestructive detection robot for pressure vessel of nuclear reactor, and detection method therefor
CN104015199A (en) * 2014-05-29 2014-09-03 中广核检测技术有限公司 Mechanical arm and detection robot based on mechanical arms
CN105810275A (en) * 2014-12-30 2016-07-27 中核武汉核电运行技术股份有限公司 Purification system for reactor cavity of reactor
CN105810275B (en) * 2014-12-30 2018-07-06 中核武汉核电运行技术股份有限公司 Reactor cavity cleaning system
CN109979616A (en) * 2017-12-27 2019-07-05 核动力运行研究所 Open frame is independently unfolded in a kind of nuclear reactor pressure container
US11187527B2 (en) * 2019-10-07 2021-11-30 The Boeing Company Multi-probe non-destructive inspection system
US11781862B2 (en) 2019-10-07 2023-10-10 The Boeing Company Multi-probe non-destructive inspection system

Similar Documents

Publication Publication Date Title
CN203465957U (en) Device for checking reactor pressure vessel of nuclear power station
CN104464849A (en) Device for checking reactor pressure vessel of nuclear power station
US10102935B2 (en) Method of removing upper internals from a nuclear reactor pressurized vessel
CN103871515B (en) A kind of reactor pressure vessel main pipeline ultrasonic examination instrument
US20130205575A1 (en) Fastening and loosening device
GB2533735A (en) Device for checking reactor pressure vessel of nuclear power station
KR102208215B1 (en) Method and apparatus for the shielded relocation of a nuclear component
CN106338719A (en) Double-supporting one-hanging object supporting rotary table for RCS measurement
US8687758B2 (en) Method for managing internal equipment in reactor pressure vessel and apparatus thereof
US9914186B2 (en) Water jet peening device
CN1841569A (en) Method and device for changing nuclear reactor upper component at least a thermoelectric couple column
JP6577014B2 (en) Method of pulling out the in-core instrument from the core of a pressurized water reactor
CN209083538U (en) Nuclear power station safety spray pump and safety injection pump units' installation measuring tool
CN102486943A (en) Automatic shifting platform for welding inspection of adapter of pressure vessel
CN201886790U (en) Automatic shifting platform for welding inspection of adapter of pressure vessel
CN204045215U (en) The syndeton of reactor pressure vessel and main pipeline
CN208752971U (en) A kind of passive type guide upright post structure
CN203024736U (en) Self-operated measuring device for radial supporting key assembly clearance
CN209892642U (en) Large-scale carousel bearing assembly work platform
CN103925412A (en) Cable tray structure for nuclear power plant reactor top cable arrangement
CN208653425U (en) A kind of cast member size detection machine work conversion equipment
CN207050601U (en) A kind of special gauge for the detection of flange shaft threaded hole position
CN207009093U (en) A kind of reactor protection tube assembly position adjustment workbench
CN208327249U (en) A kind of nuclear power plant's shielding door frame mounting tool
CN201584175U (en) Fuel rod positioning trolley

Legal Events

Date Code Title Description
GR01 Patent grant
GR01 Patent grant
CX01 Expiry of patent term
CX01 Expiry of patent term

Granted publication date: 20140305