CN205282107U - Detecting system seal tightness test end cap is revealed to reactor upper portion subassembly - Google Patents

Detecting system seal tightness test end cap is revealed to reactor upper portion subassembly Download PDF

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Publication number
CN205282107U
CN205282107U CN201520975614.1U CN201520975614U CN205282107U CN 205282107 U CN205282107 U CN 205282107U CN 201520975614 U CN201520975614 U CN 201520975614U CN 205282107 U CN205282107 U CN 205282107U
Authority
CN
China
Prior art keywords
end cap
head
stifled
leak detection
stifled head
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 - Fee Related
Application number
CN201520975614.1U
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Chinese (zh)
Inventor
吴磊
张建军
高生华
张范
赵亚明
尤晓波
张宾
刘明
李高超
易良川
孙龙
兰晓伟
曾振华
胡彬
曹晔
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.)
Jiangsu Nuclear Power Corp
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Jiangsu Nuclear Power Corp
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 Jiangsu Nuclear Power Corp filed Critical Jiangsu Nuclear Power Corp
Priority to CN201520975614.1U priority Critical patent/CN205282107U/en
Application granted granted Critical
Publication of CN205282107U publication Critical patent/CN205282107U/en
Expired - Fee Related 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

The utility model relates to a nuclear power station reactor field of overhauing, concretely relates to detecting system seal tightness test end cap is revealed to reactor upper portion subassembly. The device passes through the hub connection including extension end cap, rotatory end cap, extension end cap, rotatory end cap, and extension end cap, rotatory end cap include the location boss on upper portion. But the leak testing pipe is lived in the ground shutoff of application detecting system seal tightness test end cap is revealed to reactor upper portion subassembly convenient and fast, guarantees that seal tightness test accomplishes smoothly, reduces the activity duration of this work, the reduction radiation does that personnel receive.

Description

The stifled head of a kind of reactor upper element leak detection systems leakage test
Technical field
The utility model relates to nuclear power plant reactor maintenance field, is specifically related to the stifled head of a kind of reactor upper element leak detection systems leakage test.
Background technology
Nuclear power plant reactor upper element top cover have with lower linking tube: 121 rod drive mechanism adapters, 18 neutron temperature Measurement channel tube bank adapters, 1 reactor exhaust adapter and an exhaust for subsequent use adapter. Wherein, 121 rod drive mechanism adapters being provided with 103 rod drive mechanism pneumatic shells and 18 blind plates, 18 neutron temperature Measurement channel tube bank adapters are provided with 18 neutron temperature Measurement channel tube banks. These adapters are on average divided into 6 regions, and the stopping property that each region is designed with a set of upper element leak detection systems butt tube detects.
During annual refueling outage, in upper element inspection chamber domestic demand, the stopping property that upper element rod drive mechanism is taken over is tested, it is ensured that the integrity of primary Ioops pressure-bearing boundary during unit operation. But sealing has been untied in 18 neutron temperature Measurement channel tube banks when upper element overhauls in inspection chamber, the leak detection pipe being connected with these adapters is in mistake sealed state, therefore cannot directly upper element leak detection systems be suppressed. For this reason, Jiangsu nuclear power company limited develops the stifled head of a kind of reactor upper element leak detection systems leakage test first, ensures that upper element leak detection systems leakage test completes smoothly.
Summary of the invention
The technical problems to be solved in the utility model is to provide the stifled head of a kind of reactor upper element leak detection systems leakage test, ensure that leak detection systems leakage test can complete easily and fast, to shorten the working hour of this work, radiation dose suffered by reduction personnel.
For solving the problems of the technologies described above, the stifled head of a kind of reactor upper element leak detection systems leakage test of the utility model, this device comprises elongation and blocks up head, rotates and block up head, and head is blocked up in elongation, the stifled head of rotation is connected by axle, and head is blocked up in elongation, the positioning boss that head comprises top is blocked up in rotation.
The stifled head of described rotation comprises stifled head and axle two.
Extending stifled head and comprise stifled head and axle one, described axle one is threaded with axle two.
Axle two outside surface is provided with nut.
Packing ring is had between nut and the stifled head of elongation.
Advantageous Effects of the present utility model is: use the stifled head of reactor upper element leak detection systems leakage test can block leak detection pipe quickly and easily, ensure that leakage test completes smoothly, reduce the activity duration of this work, radiation dose suffered by reduction personnel.
Accompanying drawing explanation
Fig. 1 is upper element top cover adapter figure;
Fig. 2 is leak detection pipe interface chart;
Fig. 3 is neutron temperature Measurement channel joint pipe structure figure;
Fig. 4 is the utility model stifled head schematic diagram of a kind of reactor upper element leak detection systems leakage test;
Fig. 5 is stifled head front view;
Fig. 6 is stifled head upward view.
In figure: 1 neutron temperature Measurement channel adapter, 2 leak detection system headers, 3 leak detection pipes, 4 adapter upper end trims, the 5 lower end trims of adapter, the 6 leak detection mouths of pipe, 7 extend stifled head, 8 packing rings, 9 nuts, 10 rotate stifled head, 11 axle open holess, 12 pin-and-holes, 13 positioning boss.
Embodiment
Below in conjunction with drawings and Examples, the utility model is described in further detail.
As shown in Fig. 1,2,3,4,5,6, the stifled head of a kind of reactor upper element leak detection systems leakage test of the utility model, this end socket comprises elongation stifled 7, rotates stifled 10, extend stifled 7, rotate stifled 10 and be threaded by axle, extend stifled 7, rotate the positioning boss 13 that stifled 10 comprises top.
Rotating stifled 10 is fixed by pin with axle two by stifled head. Axle two outside surface is perfect thread structure, coordinates with nut 9, it is provided that the upper moment values needed for the leak detection mouth of pipe of sealing neutron temperature Measurement channel adapter. Axle two inside is through-hole structure, and axle one on the stifled head of elongation is freely stretched wherein. Extending stifled 9 is fixed by pin with axle one by stifled head. Being designed with positioning boss on stifled head, positioning boss can be positioned on the upper end trim of neutron temperature Measurement channel adapter, and now stifled head just blocks the leak detection mouth of pipe. Block up to withstand when the visible nut of head scantlings plan screws out by leak detection systems leakage test and extend stifled 7, make the stifled head spacing expansion in two ends thus be pressed on neutron temperature Measurement channel adapter wall, it is achieved the sealing of the leak detection mouth of pipe. Having packing ring between nut 9 and the stifled head of elongation, the packing ring that wherein nut 9 and elongation are blocked up between head plays the effect preventing nut and stifled head from killing.
During work, select to need to do the leak detection system header tested, distinguish the neutron temperature Measurement channel adapter corresponding with it, the stifled head of leak detection systems leakage test is installed, blocks the leak detection mouth of pipe; Remove leak detection system indicating instrument block; Pull down jackscrew on leakage monitoring system header, connect and suppress tracheae, start to suppress; Check that whether driving mechanism adapter stopping property is intact according to leak detection system indicating instrument.

Claims (5)

1. the stifled head of reactor upper element leak detection systems leakage test, it is characterized in that: this device comprises the stifled head (7) of elongation, rotates stifled head (10), the stifled head (7) of elongation, the stifled head (10) of rotation are connected by axle, and elongation is blocked up head (7), rotated the positioning boss (13) blocking up head (10) and comprising top.
2. the stifled head of a kind of reactor upper element leak detection systems leakage test according to claim 1, it is characterised in that: described rotation is blocked up head (10) and is comprised stifled head and axle two.
3. the stifled head of a kind of reactor upper element leak detection systems leakage test according to claim 2, it is characterised in that: extending stifled head (9) and comprise stifled head and axle one, described axle one is threaded with axle two.
4. the stifled head of a kind of reactor upper element leak detection systems leakage test according to claim 3, it is characterised in that: axle two outside surface is provided with nut (9).
5. the stifled head of a kind of reactor upper element leak detection systems leakage test according to claim 4, it is characterised in that: there is packing ring between nut (9) and the stifled head of elongation.
CN201520975614.1U 2015-11-30 2015-11-30 Detecting system seal tightness test end cap is revealed to reactor upper portion subassembly Expired - Fee Related CN205282107U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN201520975614.1U CN205282107U (en) 2015-11-30 2015-11-30 Detecting system seal tightness test end cap is revealed to reactor upper portion subassembly

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN201520975614.1U CN205282107U (en) 2015-11-30 2015-11-30 Detecting system seal tightness test end cap is revealed to reactor upper portion subassembly

Publications (1)

Publication Number Publication Date
CN205282107U true CN205282107U (en) 2016-06-01

Family

ID=56066659

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201520975614.1U Expired - Fee Related CN205282107U (en) 2015-11-30 2015-11-30 Detecting system seal tightness test end cap is revealed to reactor upper portion subassembly

Country Status (1)

Country Link
CN (1) CN205282107U (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106816189A (en) * 2015-11-30 2017-06-09 江苏核电有限公司 A kind of reactor upper element leak detection systems seal tightness test plug

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106816189A (en) * 2015-11-30 2017-06-09 江苏核电有限公司 A kind of reactor upper element leak detection systems seal tightness test plug
CN106816189B (en) * 2015-11-30 2019-02-26 江苏核电有限公司 A kind of reactor upper element leak detection systems seal tightness test plug

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GR01 Patent grant
CF01 Termination of patent right due to non-payment of annual fee
CF01 Termination of patent right due to non-payment of annual fee

Granted publication date: 20160601