CN105810259A - Detection apparatus for pressure vessel of high-temperature gas-cooled reactor - Google Patents

Detection apparatus for pressure vessel of high-temperature gas-cooled reactor Download PDF

Info

Publication number
CN105810259A
CN105810259A CN201410842508.6A CN201410842508A CN105810259A CN 105810259 A CN105810259 A CN 105810259A CN 201410842508 A CN201410842508 A CN 201410842508A CN 105810259 A CN105810259 A CN 105810259A
Authority
CN
China
Prior art keywords
pressure vessel
elevating lever
guide rail
axle
scanners
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.)
Granted
Application number
CN201410842508.6A
Other languages
Chinese (zh)
Other versions
CN105810259B (en
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
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 CN201410842508.6A priority Critical patent/CN105810259B/en
Publication of CN105810259A publication Critical patent/CN105810259A/en
Application granted granted Critical
Publication of CN105810259B publication Critical patent/CN105810259B/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 specifically relates to a detection apparatus for a pressure vessel of a high-temperature gas-cooled reactor, which belongs to the field of detection apparatuses for pressure vessels. The detection apparatus 1 is located between a pressure vessel outer barrel wall 2 and a cabin barrel wall 3 and comprises an annular guide rail 4, a rail-running trolley 5, a lifting bar 6, a two-shaft scanner 7 and a positioning pin pointing mechanism 8, wherein the annular guide rail 4 is a whole circular ring formed by splicing of a plurality of arc guide rails; the rail-running trolley 5 is located on the annular guide rail 4 and can move along the rail; and the lifting bar 6 is mounted on the rail-running trolley 5, and the lower end of the lifting bar 6 is provided with the positioning pin pointing mechanism 8 which can be fixed with a positioning pin hole located in the bottom of the pressure vessel. According to the invention, the lower end of the lifting bar 6 is provided with the positioning pin pointing mechanism 8 which can be fixed with the positioning pin hole located in the bottom of the pressure vessel.

Description

A kind of HTGR reactor pressure vessel checks device
Technical field
This technology belongs to pressure vessel and checks device field, is specifically related to a kind of HTGR reactor pressure vessel and checks device.
Background technology
HTGR is to make coolant 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 the research of high-temperature gas-solid two-phase flow, exploitation, one of technology of forth generation Advanced Nuclear Energy Systems.This heap-type equally exists the nuclear reactor pressure container (reactorpressurevessel) of similar presurized water reactor.Reactor pressure vessel is to dispose nuclear reaction and bear the hermetic container of its huge operating pressure, it it is the key equipment in HTGR Nuclear Power Plant, have that manufacturing technology standard is high, difficulty big and the feature such as cycle length, and be non-exchange equipment, it is necessary to assure it is perfectly safe reliable in the nuclear power station lifetime more than 40 years.
In nuclear power station running, reactor pressure vessel is in high temperature, high pressure, the high environment radiated.Increase along with the time of operation, the metallicity of container material can be gradually lowered, metal discontinuity also can produce, so being extremely necessary pressure vessel is detected, to find defect risk therein in time, can be processed as early as possible, thus safeguarding and ensure the safety of nuclear power facility, it is to avoid serious safe operation and nuclear leakage accident occur.
Nuclear reactor pressure container is after power station is run, and internal tank is high radioactivity region, owing to high temperature nuclear reactor uses helium to make coolant, and is absent from out the feature of container unloading shutdown.HTGR reactor pressure vessel checks to be implemented from outside of containers.Summary situation need a set of can Remote implement reactor pressure vessel check device, the current world is not about HTGR commercialization power station reactor pressure vessel Examined effect, being required for this heap-type independent design and go out a kind of nuclear power plant reactor pressure vessel inspection device, this inspection device checks from outside enforcement of pressure vessel.
Summary of the invention
It is an object of the invention to: provide a kind of HTGR reactor pressure vessel to check device, implement Nuclear Power Station reactor pressure vessel and check.
Technical scheme is as follows: a kind of HTGR reactor pressure vessel checks device, check that device is between pressure vessel outer tube wall and cabin barrel, checking that device includes ring-shaped guide rail, track operation dolly, elevating lever, two axle scanners, alignment pin directing mechanism, ring-shaped guide rail is to be 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 is installed elevating lever, alignment pin directing mechanism is carried in elevating lever lower end, can fix with pressure vessel bottom alignment pin control, whole elevating lever is made to keep vertical state, realize the track operation dolly accurate subregion on container excircle, two axle scanners are arranged on elevating lever, it installs scanning module, can be used for checking.
Described elevating lever adopts the aluminium section bar of tetragon column, more piece assemble, thus forming the long tooth bar lead from reactor compartment roof to lower vessel portion.
Described axle scanner is circular arc type structure, and including front jacking mechanism, rear jacking mechanism, motor, scanning module, upright guide rail, two axle scanners are arranged on elevating lever, motor-driven gear, makes two axle scanners can move up and down along elevating lever;The front jacking mechanism of two axle scanners is tentacle shape structure, it is positioned at the left and right sides of two axle scanner circular arc type structures, can be used for stretch pressure container outer tube wall, two axle scanner circular arc type structures 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 two axle scanners, can horizontal movement on circular arc, and scanning module is positioned on upright guide rail, can move up and down along upright guide rail.
Described two axle scanners are arranged on elevating lever, and are mediated by rack-and-pinion between elevating lever, guide wheel rolling support.
The remarkable result of the present invention is in that: forms of motion is simple, and Bit andits control is accurate, it is not necessary to additional coordinates is changed.Elevating lever automatic lifting assembly arranged by track operation dolly, two direction of motion combinations, it is achieved scanning axle is implemented container outer surface any position and checked simultaneously.
Accompanying drawing explanation
Fig. 1 is that a kind of HTGR reactor pressure vessel of the present invention checks device schematic diagram
Fig. 2 is that a kind of HTGR reactor pressure vessel of the present invention checks apparatus structure schematic diagram
Fig. 3 is that a kind of HTGR reactor pressure vessel of the present invention checks device two axle scanner structural representation
In figure: 1 checks device, 2 pressure vessel outer tube walls, 3 cabin barrels, 4 ring-shaped guide rails, 5 track operation dollies, 6 elevating levers, 7 liang of axle scanners, 8 alignment pin directing mechanisms, jacking mechanism before 9, jacking mechanism, 11 motors, 12 scanning modules, 13 upright guide rails after 10
Detailed description of the invention
Below in conjunction with drawings and the specific embodiments, the present invention is described in further detail.
As shown in Figure 1, a kind of HTGR reactor pressure vessel checks device, check during inspection that device 1 is between pressure vessel outer tube wall 2 and cabin barrel 3, checking that device 1 includes ring-shaped guide rail 4, track operation dolly 5, elevating lever 6, two axle scanner 7, alignment pin directing mechanism 8, ring-shaped guide rail 4 is to be 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 tetragon column, assembled by more piece, thus forming the long tooth bar lead from reactor compartment roof to lower vessel portion, alignment pin directing mechanism 8 is carried in elevating lever 6 lower end, can fix with pressure vessel bottom alignment pin control so that whole elevating lever 6 keeps vertical state, it is achieved the track operation dolly 5 accurate subregion on container excircle.
As shown in Figure 3, two axle scanners 7 are circular arc type structure, including front jacking mechanism 9, rear jacking mechanism 10, motor 11, scanning module 12, upright guide rail 13, two axle scanners 7 are arranged on elevating lever 6, and mediated by rack-and-pinion between elevating lever 6, guide wheel rolling support, motor 11 drives gear, makes two axle scanners 7 can move up and down along elevating lever 6;The front jacking mechanism 9 of two axle scanners 7 is tentacle shape structure, it is positioned at the left and right sides of two axle scanner 7 circular arc type structures, can be used for stretch pressure container outer tube wall 2, two axle scanner 7 circular arc type structures 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 two axle scanners 7, can horizontal 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 two axle scanners 7, moves to inspection position, and elevating lever 6 positions, two axle scanners 7 move to relevant position under the driving of motor 11, and front jacking mechanism 9, rear jacking mechanism 10 are implemented to check after holding out against cabin barrel 3 and pressure vessel outer tube wall 2.

Claims (4)

1. a HTGR reactor pressure vessel checks device, check that device (1) is positioned between pressure vessel outer tube wall (2) and cabin barrel (3), it is characterized in that: checking that device (1) includes ring-shaped guide rail (4), track operation dolly (5), elevating lever (6), two axle scanners (7), alignment pin directing mechanism (8), ring-shaped guide rail (4) is to be 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), alignment pin directing mechanism (8) is carried in elevating lever (6) lower end, can fix with pressure vessel bottom alignment pin control, whole elevating lever (6) is made to keep vertical state, realize the track operation dolly 5 accurate subregion on container excircle, two axle scanners (7) are arranged on elevating lever (6), it installs scanning module (12), can be used for checking.
2. a kind of HTGR reactor pressure vessel according to claim 1 checks device, it is characterized in that: described elevating lever (6) adopts the aluminium section bar of tetragon column, assembled by more piece, thus forming the long tooth bar lead from reactor compartment roof to lower vessel portion.
3. a kind of HTGR reactor pressure vessel according to claim 2 checks device, it is characterized in that: described axle scanner (7) is circular arc type structure, including front jacking mechanism (9), rear jacking mechanism (10), motor (11), scanning module (12), upright guide rail (13), two axle scanners (7) are arranged on elevating lever (6), motor (11) drives gear, makes two axle scanners (7) can move up and down along elevating lever (6);The front jacking mechanism (9) of two axle scanners (7) is tentacle shape structure, it is positioned at the left and right sides of two axle scanner (7) circular arc type structures, can be used for stretch pressure container outer tube wall (2), two axle scanner (7) circular arc type structures 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 two axle scanners (7), can horizontal 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 HTGR reactor pressure vessel according to claim 3 checks device, it is characterized in that: described two axle scanners (7) are arranged on elevating lever (6), and elevating lever is mediated by rack-and-pinion between (6), guide wheel rolling support.
CN201410842508.6A 2014-12-30 2014-12-30 A kind of HTGR reactor pressure vessel check device Active CN105810259B (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201410842508.6A CN105810259B (en) 2014-12-30 2014-12-30 A kind of HTGR reactor pressure vessel check device

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201410842508.6A CN105810259B (en) 2014-12-30 2014-12-30 A kind of HTGR reactor pressure vessel check device

Publications (2)

Publication Number Publication Date
CN105810259A true CN105810259A (en) 2016-07-27
CN105810259B CN105810259B (en) 2017-12-22

Family

ID=56419887

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201410842508.6A Active CN105810259B (en) 2014-12-30 2014-12-30 A kind of HTGR reactor pressure vessel check device

Country Status (1)

Country Link
CN (1) CN105810259B (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108098786A (en) * 2017-12-19 2018-06-01 扬州大学 Fusion reactor peeps mechanical arm in
CN108257693A (en) * 2016-12-29 2018-07-06 核动力运行研究所 A kind of reactor pressure vessel outer surface scanning equipment
CN109448875A (en) * 2018-12-21 2019-03-08 核动力运行研究所 A kind of anti-drop structure for welding line detector
CN111380954A (en) * 2018-12-28 2020-07-07 核动力运行研究所 Ultrasonic automatic inspection device for pressure vessel of high-temperature gas cooled reactor nuclear reactor
CN111383785A (en) * 2018-12-28 2020-07-07 核动力运行研究所 Circular motion trolley for checking pressure container

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4507260A (en) * 1981-04-08 1985-03-26 Hitachi, Ltd. Rail apparatus around reactor pressure vessel
JPS62116296A (en) * 1985-11-16 1987-05-27 バブコツク日立株式会社 Monitor test piece detachable device for pressure vessel of nuclear reactor
CN202487186U (en) * 2011-12-28 2012-10-10 核动力运行研究所 Ultrasonic testing tool for welding line of safety injection pipe of pressure vessel in nuclear power station
CN203733482U (en) * 2013-12-30 2014-07-23 中核武汉核电运行技术股份有限公司 Ultrasonic detection device for welding seam of pressure container joint pipe
CN204375430U (en) * 2014-12-30 2015-06-03 中核武汉核电运行技术股份有限公司 A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4507260A (en) * 1981-04-08 1985-03-26 Hitachi, Ltd. Rail apparatus around reactor pressure vessel
JPS62116296A (en) * 1985-11-16 1987-05-27 バブコツク日立株式会社 Monitor test piece detachable device for pressure vessel of nuclear reactor
CN202487186U (en) * 2011-12-28 2012-10-10 核动力运行研究所 Ultrasonic testing tool for welding line of safety injection pipe of pressure vessel in nuclear power station
CN203733482U (en) * 2013-12-30 2014-07-23 中核武汉核电运行技术股份有限公司 Ultrasonic detection device for welding seam of pressure container joint pipe
CN204375430U (en) * 2014-12-30 2015-06-03 中核武汉核电运行技术股份有限公司 A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN108257693A (en) * 2016-12-29 2018-07-06 核动力运行研究所 A kind of reactor pressure vessel outer surface scanning equipment
CN108257693B (en) * 2016-12-29 2023-09-08 核动力运行研究所 Reactor pressure vessel surface scanning device
CN108098786A (en) * 2017-12-19 2018-06-01 扬州大学 Fusion reactor peeps mechanical arm in
CN108098786B (en) * 2017-12-19 2020-12-04 扬州大学 Endoscopic mechanical arm for fusion reactor
CN109448875A (en) * 2018-12-21 2019-03-08 核动力运行研究所 A kind of anti-drop structure for welding line detector
CN109448875B (en) * 2018-12-21 2024-04-09 核动力运行研究所 Anti-falling structure for welding line detection equipment
CN111380954A (en) * 2018-12-28 2020-07-07 核动力运行研究所 Ultrasonic automatic inspection device for pressure vessel of high-temperature gas cooled reactor nuclear reactor
CN111383785A (en) * 2018-12-28 2020-07-07 核动力运行研究所 Circular motion trolley for checking pressure container

Also Published As

Publication number Publication date
CN105810259B (en) 2017-12-22

Similar Documents

Publication Publication Date Title
CN105810259A (en) Detection apparatus for pressure vessel of high-temperature gas-cooled reactor
US11342082B2 (en) Control rod drive mechanism (CRDM) mounting method for pressurized water reactors
CN203465957U (en) Device for checking reactor pressure vessel of nuclear power station
CN108257693B (en) Reactor pressure vessel surface scanning device
CN104751915B (en) Automatic ultrasonic testing equipment for threaded hole zone of nuclear reactor pressure vessel
CN109326362B (en) Nuclear fusion device inner part teleoperation transfer device based on annular separable track
CN105261400A (en) Remote operation transfer scheme for component maintenance of nuclear fusion apparatus
CN104051035A (en) Reactor core assembly replacing device for liquid-state heavy metal reactor
CN206524189U (en) A kind of reactor pressure vessel outer surface scanning equipment
CN102717807B (en) Transfer car for spent fuel storage tank
CN204375430U (en) A kind of high temperature gas cooled reactor reactor pressure vessel testing fixture
US20150321299A1 (en) Water jet peening device
CN208000750U (en) A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system
CN106504807A (en) Graphite more changing device on the outside of a kind of HTGR
US9318226B2 (en) Apparatus and method to inspect, modify, or repair nuclear reactor core shrouds
CN202601222U (en) Neutron fluence rate detector positioning structure of ex-reactor nuclear instrumentation system
CN109979626A (en) A kind of swimming pool formula atmospheric low-temperature process heat reactor fuel handling system and method
CN104332185B (en) The leading experiment porch of following fusion reactor divertor parts military service performance
CN101673584A (en) Closed circuit television inspection device
CN204732178U (en) VVER core barrel outside surface video inspection device
CN116189937A (en) High-temperature gas cooled reactor pressure vessel ultrasonic inspection couplant circulation system
CN102486943A (en) Automatic shifting platform for welding inspection of adapter of pressure vessel
CN108254436B (en) Cable device for vortex detection of horizontal steam generator heat transfer tube
CN208752971U (en) A kind of passive type guide upright post structure
CN206574493U (en) A kind of connection strap and reactor pressure vessel inspection quick-connect machanism

Legal Events

Date Code Title Description
C06 Publication
PB01 Publication
C10 Entry into substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant