CN202647706U - Quake-proof strip for novel nuclear power station steam generator - Google Patents

Quake-proof strip for novel nuclear power station steam generator Download PDF

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Publication number
CN202647706U
CN202647706U CN2012202133822U CN201220213382U CN202647706U CN 202647706 U CN202647706 U CN 202647706U CN 2012202133822 U CN2012202133822 U CN 2012202133822U CN 201220213382 U CN201220213382 U CN 201220213382U CN 202647706 U CN202647706 U CN 202647706U
Authority
CN
China
Prior art keywords
quake
proof strip
steam generator
power station
vibration strip
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
CN2012202133822U
Other languages
Chinese (zh)
Inventor
华大凤
王树平
绍兴明
华鹏
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 XINHUA ALLOY ELECTRIC APPARATUS CO Ltd
Original Assignee
JIANGSU XINHUA ALLOY ELECTRIC APPARATUS 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 JIANGSU XINHUA ALLOY ELECTRIC APPARATUS CO Ltd filed Critical JIANGSU XINHUA ALLOY ELECTRIC APPARATUS CO Ltd
Priority to CN2012202133822U priority Critical patent/CN202647706U/en
Application granted granted Critical
Publication of CN202647706U publication Critical patent/CN202647706U/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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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
    • 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
    • Y02PCLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P80/00Climate change mitigation technologies for sector-wide applications
    • Y02P80/10Efficient use of energy, e.g. using compressed air or pressurized fluid as energy carrier
    • Y02P80/15On-site combined power, heat or cool generation or distribution, e.g. combined heat and power [CHP] supply

Abstract

The utility model discloses a quake-proof strip for a novel nuclear power station steam generator. The quake-proof strip comprises a quake-proof strip body and end caps, wherein the quake-proof strip body has a U-shaped included angle, and each end cap penetrates through two ends of the quake-proof strip body to be pressed and fixed on the quake-proof strip body. Each end cap is fixed on the quake-proof strip body through a central press point, and first press points capable of preventing the end caps from sliding up and down are symmetrically arranged on the left side and the right side of each end of the quake-proof strip body. The quake-proof strip has the advantages of being simple to manufacture, high in safety and capable of effectively having the quake-proof effects and avoiding large economical loss.

Description

A kind of nucleus power station steam generator anti-vibration strip
Technical field
The utility model relates to a kind of nucleus power station steam generator anti-vibration strip.
Background technology
AP1000 is the third generation million kilowatt advanced pressurized water reactor nuclear power generating sets of US Westinghouse company's exploitation.AP1000 is different from the security system that the main feature that two generations added CPR1000 compressed water reactor nuclear power unit is exactly " non-active "." non-active " design concept is exactly to utilize intrinsic hot-working hydraulic characteristic, simplify the design of security system, make nuclear power station guarantee that the measure of safety no longer relies on the operation of the active equipment such as pump, blower fan, thereby reduced significantly valve, pump, cable and the antidetonation factory building of safe level; Cancelled 1E level emergency diesel dynamo system; Reduced the active equipment of most of safe level; Reduced large material usage; System simplification makes design simplification, technology arrangement simplification, construction volume minimizing, operation and also corresponding minimizing of maintenance capacity.
Steam generator is the nuclear power station key equipment, also be one of the maximum equipment that breaks down in the nuclear power station device, its effect is that handle is passed to secondary circuit water by the heat of the cooling agent of reactor, and makes it to become steam, passes into the cylinder work done of steam turbine generator again.
The service behaviour of steam generator and security reliability are vital for the safe and stable operation of whole yarn system.A nuclear power station need arrange several steam generators, include ten hundreds of heat-transfer pipes, heat-transfer pipe is U-shaped pipe, it is the critical piece of nuclear power station steam generator, the high-temperature setting-out flows in tube bank, flow with vertical direction along pipe for feedwater, be heated simultaneously, then be vaporized, steam enters the steam turbine generating, the fluid that contacts with these pipes can cause vibrations, break because vibrations can cause damaged tubular, directly cause steam generator and damage, change a steam generator and need 200,000,000 dollars expenses, need the shutdown some months, cause great economic loss.
Break in order to prevent that effectively pipe from shaking, the configuration anti-vibration strip comes support tube between the adjacent row of pipe, anti-vibration strip is set the nuclear plant safety reliability service is played key effect.
The utility model content
A kind of nucleus power station steam generator anti-vibration strip that provides of the present utility model is made simple, reasonable in design and production cost is low, and more effectively the heat-transfer pipe of supported steam generator reaches shockproof purpose.
The utility model is achieved through the following technical solutions: a kind of nucleus power station steam generator anti-vibration strip, comprise anti-vibration strip and end cap, wherein said anti-vibration strip has U-shaped angle, and each described end cap passes from the two ends of described anti-vibration strip respectively and pressing is fixed on the described anti-vibration strip.
Wherein each described end cap be fixed on the described anti-vibration strip by the center pressure point and the left and right sides of the every end of described anti-vibration strip on all be symmetrically arranged with the first pressure point that prevents that end cap from sliding up and down.
The U-shaped angle of described anti-vibration strip be 10 ° 53 '.
The beneficial effects of the utility model are: make simple, the safe shockproof effect of more effectively opening, avoid causing huge economic loss.
Description of drawings
Fig. 1 is the structural representation of the utility model embodiment;
Wherein 1-anti-vibration strip, 2-end cap, 3-center pressure point, 4-the first pressure point.
The specific embodiment
Below in conjunction with accompanying drawing the utility model is described in further detail:
As shown in Figure 1: a kind of nucleus power station steam generator anti-vibration strip of the present embodiment, comprise that anti-vibration strip 1, end cap 2, wherein said anti-vibration strip 1 have U-shaped angle, described U-shaped angle be 10 ° 53 ', each described end cap 2 passes from the two ends of described anti-vibration strip 1 respectively and is fixed on the described anti-vibration strip 1 by center pressure point 3.
All be symmetrically arranged with the first pressure point 4 that prevents that end cap 2 from sliding up and down on the left and right sides of described anti-vibration strip 1 every end.
The beneficial effect of the present embodiment is: easily be shaped, safe and make simply, anti seismic efficiency is more remarkable.

Claims (3)

1. nucleus power station steam generator anti-vibration strip, comprise that anti-vibration strip (1) is characterized in that: also comprise end cap (2), wherein said anti-vibration strip (1) has U-shaped angle, and each described end cap (2) passes from the two ends of described anti-vibration strip (1) respectively and pressing is fixed on the described anti-vibration strip (1).
2. a kind of nucleus according to claim 1 power station steam generator anti-vibration strip is characterized in that: each described end cap (2) is fixed on by center pressure point (3) on the left and right sides of the upper and every end of described anti-vibration strip (1) of described anti-vibration strip (1) and all is symmetrically arranged with the first pressure point (4) that prevents that end cap (2) from sliding up and down.
3. a kind of nucleus according to claim 1 and 2 power station steam generator anti-vibration strip is characterized in that: the U-shaped angle of described anti-vibration strip (1) be 10 ° 53 '.
CN2012202133822U 2012-05-14 2012-05-14 Quake-proof strip for novel nuclear power station steam generator Expired - Fee Related CN202647706U (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN2012202133822U CN202647706U (en) 2012-05-14 2012-05-14 Quake-proof strip for novel nuclear power station steam generator

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN2012202133822U CN202647706U (en) 2012-05-14 2012-05-14 Quake-proof strip for novel nuclear power station steam generator

Publications (1)

Publication Number Publication Date
CN202647706U true CN202647706U (en) 2013-01-02

Family

ID=47416807

Family Applications (1)

Application Number Title Priority Date Filing Date
CN2012202133822U Expired - Fee Related CN202647706U (en) 2012-05-14 2012-05-14 Quake-proof strip for novel nuclear power station steam generator

Country Status (1)

Country Link
CN (1) CN202647706U (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106653128A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 Anti-vibration bar assembly for ACP1000 nuclear power plant and method for producing same
CN106624601A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 Anti-vibration strip assembly for nuclear power station and production method thereof
CN106624603A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 ACP1000 anti-vibration strip assembly and production method thereof
CN106624602A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 Vibration-resistant bar component for water reactor nuclear power plant ACP1000 and production method of component
CN106653127A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 Anti-vibration strip assembly for ACP1000 nuclear power station and production method thereof

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN106653128A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 Anti-vibration bar assembly for ACP1000 nuclear power plant and method for producing same
CN106624601A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 Anti-vibration strip assembly for nuclear power station and production method thereof
CN106624603A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 ACP1000 anti-vibration strip assembly and production method thereof
CN106624602A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 Vibration-resistant bar component for water reactor nuclear power plant ACP1000 and production method of component
CN106653127A (en) * 2015-10-28 2017-05-10 丹阳市龙鑫合金有限公司 Anti-vibration strip assembly for ACP1000 nuclear power station and production method thereof
CN106653127B (en) * 2015-10-28 2018-03-23 丹阳市龙鑫合金有限公司 A kind of ACP1000 used in nuclear power station antivibration bar assembly and its production method
CN106653128B (en) * 2015-10-28 2018-03-23 丹阳市龙鑫合金有限公司 ACP1000 used in nuclear power station antivibration bar assemblies and its production method

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Legal Events

Date Code Title Description
C14 Grant of patent or utility model
GR01 Patent grant
C53 Correction of patent for invention or patent application
CB03 Change of inventor or designer information

Inventor after: Hua Dafeng

Inventor after: Wang Shuping

Inventor after: Shao Xingming

Inventor after: Hua Peng

Inventor before: Hua Dafeng

Inventor before: Wang Shuping

Inventor before: Shao Xingming

Inventor before: Hua Peng

C56 Change in the name or address of the patentee
CP02 Change in the address of a patent holder

Address after: 225722 No. 19, Zhang Guo, South Town, Jiangsu, Xinghua

Patentee after: Jiangsu Xinhua Alloy Electric Apparatus Co., Ltd.

Address before: 225722 No. 19, Zhang Guo, South Town, Jiangsu, Taizhou

Patentee before: Jiangsu Xinhua Alloy Electric Apparatus Co., Ltd.

C17 Cessation of patent right
CF01 Termination of patent right due to non-payment of annual fee

Granted publication date: 20130102

Termination date: 20130514