CN204375430U - A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture - Google Patents

A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture Download PDF

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Publication number
CN204375430U
CN204375430U CN201420859739.3U CN201420859739U CN204375430U CN 204375430 U CN204375430 U CN 204375430U CN 201420859739 U CN201420859739 U CN 201420859739U CN 204375430 U CN204375430 U CN 204375430U
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CN
China
Prior art keywords
elevating lever
pressure vessel
scanner
guide rail
diaxon
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.)
Withdrawn - After Issue
Application number
CN201420859739.3U
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Chinese (zh)
Inventor
王俊涛
周文
张志义
王庆武
徐安
朱琳
贾晶晶
尹鹏
徐华锋
文斌
孙海漩
杨光
李铮
张军
林百涛
陈凯
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
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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 CN201420859739.3U priority Critical patent/CN204375430U/en
Application granted granted Critical
Publication of CN204375430U publication Critical patent/CN204375430U/en
Withdrawn - After Issue legal-status Critical Current
Anticipated expiration legal-status Critical

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    • 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

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  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

This technology belongs to pressure vessel testing fixture field, is specifically related to a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture.Testing fixture 1 is between pressure vessel outer tube wall 2 and cabin barrel 3, testing fixture 1 comprises ring-shaped guide rail 4, track operation dolly 5, elevating lever 6, diaxon scanner 7, register pin directing mechanism 8, and ring-shaped guide rail 4 is spliced into whole annulus by multi-disc arc guide rail; Track operation dolly 5 is positioned on ring-shaped guide rail 4, can orbital motion; Track transportation trolley 5 is installed elevating lever 6, and register pin directing mechanism 8 is carried in elevating lever 6 lower end, can fix with the control of pressure vessel bottom register pin.Register pin directing mechanism 8 is carried in the utility model elevating lever 6 lower end, can fix with the control of pressure vessel bottom register pin.

Description

A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture
Technical field
This technology belongs to pressure vessel testing fixture field, is specifically related to a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture.
Background technology
High temperature gas cooled reactor makes cooling medium with helium, the nuclear reactor that outlet temperature is high.Under the support of national " 863 " plan, from the eighties mid-term in last century, China has carried out research, the exploitation of high-temperature gas-solid two-phase flow, one of technology of forth generation Advanced Nuclear Energy Systems.There is the nuclear reactor pressure container (reactor pressure vessel) of similar presurized water reactor equally in this heap-type.Reactor pressure vessel is the closed container settled nuclear reaction and bear its huge operating pressure, it is the key equipment in HTGR 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 ensure that it is perfectly safe reliably in the lifetime of nuclear power station more than 40 years.
In nuclear power station operational process, reactor pressure vessel is in the environment of high temperature, high pressure, high radiation.Along with the increase of working time, the metallicity of container material can reduce gradually, metal uncontinuity also can produce, so be extremely necessary to detect pressure vessel, with Timeliness coverage defect risk wherein, can be processed as early as possible, thus be safeguarded and ensure the safety of nuclear power facility, avoid occurring serious safe operation and nuclear leakage accident.
Nuclear reactor pressure container is after power station is run, and internal tank is high radioactivity region, because high temperature nuclear reactor uses helium to make cooling medium, and there is not out the feature of container unloading shutdown.The inspection of high temperature gas cooled reactor reactor pressure vessel is implemented from outside of containers.Comprehensive above-mentioned situation need a set of can the device that checks of the reactor pressure vessel implemented of Remote, the current world is not about high temperature gas cooled reactor commercial power station reactor pressure vessel Examined effect, need to go out a kind of nuclear power plant reactor pressure vessel testing fixture for this heap-type independent design, this testing fixture is implemented to check from pressure vessel outside.
Summary of the invention
The purpose of this utility model is: provide a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture, implements the inspection of Nuclear Power Station reactor pressure vessel.
The technical solution of the utility model is as follows: a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture, testing fixture is between pressure vessel outer tube wall and cabin barrel, testing fixture comprises ring-shaped guide rail, track operation dolly, elevating lever, diaxon scanner, register pin directing mechanism, and ring-shaped guide rail is spliced into whole annulus by multi-disc arc guide rail; Track operation dolly is positioned on ring-shaped guide rail, can orbital motion; Track transportation trolley installs elevating lever, register pin directing mechanism is carried in elevating lever lower end, can fix with the control of pressure vessel bottom register pin, whole elevating lever is made to keep vertical state, realize the accurate subregion of track operation dolly on container excircle, diaxon scanner is arranged on elevating lever, and it installs scanning module, can be used for checking.
Described elevating lever adopts the aluminium section bar of quadrilateral column, is assembled by more piece, thus forms the long tooth bar guidepost from reactor compartment roof to lower vessel portion.
Described axle scanner is circular arc type structure, and comprise front jacking mechanism, rear jacking mechanism, motor, scanning module, upright guide rail, diaxon scanner is arranged on elevating lever, motor-driven gear, and diaxon scanner can be moved up and down along elevating lever; The front jacking mechanism of diaxon scanner is tentacle shape structure, be positioned at the left and right sides of diaxon scanner circular arc type structure, can be used for stretch pressure container outer tube wall, diaxon scanner circular arc type structure middle part on rear side of be rear jacking mechanism, it is two tentacle shape structures backward, can be used for holding out against cabin barrel, upright guide rail is positioned on the circular arc of diaxon scanner, can tangential movement on circular arc, and scanning module is positioned on upright guide rail, can move up and down along upright guide rail.
Described diaxon scanner is arranged on elevating lever, and is mediated by rack-and-pinion between elevating lever, guide wheel rolling support.
Remarkable result of the present utility model is: forms of motion is simple, and Bit andits control is accurate, does not need additional coordinates to change.Elevating lever automatic lifting assembly arranged by track operation dolly, two direction of motion combinations simultaneously, realize scanning axle and implement the inspection of container outer surface any position.
Accompanying drawing explanation
Fig. 1 is a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture schematic diagram described in the utility model
Fig. 2 is a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture structural representation described in the utility model
Fig. 3 is a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture diaxon scanner structural representation described in the utility model
In figure: jacking mechanism, 10 rear jacking mechanism, 11 motors, 12 scanning modules, 13 upright guide rails before 1 testing fixture, 2 pressure vessel outer tube walls, 3 cabin barrels, 4 ring-shaped guide rails, 5 track operation dollies, 6 elevating levers, 7 diaxon scanners, 8 register pin directing mechanisms, 9
Embodiment
Below in conjunction with drawings and the specific embodiments, the utility model is described in further detail.
As shown in Figure 1, a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture, during inspection, testing fixture 1 is between pressure vessel outer tube wall 2 and cabin barrel 3, testing fixture 1 comprises ring-shaped guide rail 4, track operation dolly 5, elevating lever 6, diaxon scanner 7, register pin directing mechanism 8, and ring-shaped guide rail 4 is spliced into whole annulus by multi-disc arc guide rail; Track operation dolly 5 is positioned on ring-shaped guide rail 4, can orbital motion; Track transportation trolley 5 is installed elevating lever 6, elevating lever 6 adopts the aluminium section bar of quadrilateral column, assembled by more piece, thus the long tooth bar guidepost formed from reactor compartment roof to lower vessel portion, register pin directing mechanism 8 is carried in elevating lever 6 lower end, can fix with the control of pressure vessel bottom register pin, make whole elevating lever 6 keep vertical state, realize the accurate subregion of track operation dolly 5 on container excircle.
As shown in Figure 3, diaxon scanner 7 is circular arc type structure, comprise front jacking mechanism 9, rear jacking mechanism 10, motor 11, scanning module 12, upright guide rail 13, diaxon scanner 7 is arranged on elevating lever 6, and mediated by rack-and-pinion between elevating lever 6, guide wheel rolling support, motor 11 driven wheel, makes diaxon scanner 7 can move up and down along elevating lever 6; The front jacking mechanism 9 of diaxon scanner 7 is tentacle shape structure, be positioned at the left and right sides of diaxon scanner 7 circular arc type structure, can be used for stretch pressure container outer tube wall 2, diaxon scanner 7 circular arc type structure middle part on rear side of be rear jacking mechanism 10, it is two tentacle shape structures backward, can be used for holding out against cabin barrel 3, upright guide rail 13 is positioned on the circular arc of diaxon scanner 7, can tangential movement on circular arc, and scanning module 12 is positioned on upright guide rail 13, can move up and down along upright guide rail 13.
During inspection, track operation dolly 5 carries elevating lever 6 and diaxon scanner 7, move to and check position, elevating lever 6 is located, diaxon scanner 7 moves to relevant position under the driving of motor 11, and front jacking mechanism 9, rear jacking mechanism 10 are implemented after holding out against cabin barrel 3 and pressure vessel outer tube wall 2 to check.

Claims (4)

1. a high temperature gas cooled reactor reactor pressure vessel testing fixture, testing fixture (1) is positioned between pressure vessel outer tube wall (2) and cabin barrel (3), it is characterized in that: testing fixture (1) comprises ring-shaped guide rail (4), track operation dolly (5), elevating lever (6), diaxon scanner (7), register pin directing mechanism (8), ring-shaped guide rail (4) is spliced into whole annulus by multi-disc arc guide rail; Track operation dolly (5) is positioned on ring-shaped guide rail (4), can orbital motion; Track transportation trolley (5) is installed elevating lever (6), register pin directing mechanism (8) is carried in elevating lever (6) lower end, can fix with the control of pressure vessel bottom register pin, whole elevating lever (6) is made to keep vertical state, realize the accurate subregion of track operation dolly 5 on container excircle, diaxon scanner (7) is arranged on elevating lever (6), it installs scanning module (12), can be used for checking.
2. a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture according to claim 1, it is characterized in that: described elevating lever (6) adopts the aluminium section bar of quadrilateral column, assembled by more piece, thus form the long tooth bar guidepost from reactor compartment roof to lower vessel portion.
3. a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture according to claim 2, it is characterized in that: described axle scanner (7) is circular arc type structure, comprise front jacking mechanism (9), rear jacking mechanism (10), motor (11), scanning module (12), upright guide rail (13), diaxon scanner (7) is arranged on elevating lever (6), motor (11) driven wheel, makes diaxon scanner (7) can move up and down along elevating lever (6), the front jacking mechanism (9) of diaxon scanner (7) is tentacle shape structure, be positioned at the left and right sides of diaxon scanner (7) circular arc type structure, can be used for stretch pressure container outer tube wall (2), diaxon scanner (7) circular arc type structure middle part on rear side of be rear jacking mechanism (10), it is two tentacle shape structures backward, can be used for holding out against cabin barrel (3), upright guide rail (13) is positioned on the circular arc of diaxon scanner (7), can tangential movement on circular arc, and scanning module (12) is positioned on upright guide rail (13), can move up and down along upright guide rail (13).
4. a kind of high temperature gas cooled reactor reactor pressure vessel testing fixture according to claim 3, it is characterized in that: described diaxon scanner (7) is arranged on elevating lever (6), and elevating lever is mediated by rack-and-pinion between (6), guide wheel rolling support.
CN201420859739.3U 2014-12-30 2014-12-30 A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture Withdrawn - After Issue CN204375430U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201420859739.3U CN204375430U (en) 2014-12-30 2014-12-30 A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201420859739.3U CN204375430U (en) 2014-12-30 2014-12-30 A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture

Publications (1)

Publication Number Publication Date
CN204375430U true CN204375430U (en) 2015-06-03

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105810259A (en) * 2014-12-30 2016-07-27 中核武汉核电运行技术股份有限公司 Detection apparatus for pressure vessel of high-temperature gas-cooled reactor

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN105810259A (en) * 2014-12-30 2016-07-27 中核武汉核电运行技术股份有限公司 Detection apparatus for pressure vessel of high-temperature gas-cooled reactor

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C14 Grant of patent or utility model
GR01 Patent grant
AV01 Patent right actively abandoned
AV01 Patent right actively abandoned

Granted publication date: 20150603

Effective date of abandoning: 20171222