CN111425603A - 一种一体化压力边界隔离阀 - Google Patents

一种一体化压力边界隔离阀 Download PDF

Info

Publication number
CN111425603A
CN111425603A CN202010339104.0A CN202010339104A CN111425603A CN 111425603 A CN111425603 A CN 111425603A CN 202010339104 A CN202010339104 A CN 202010339104A CN 111425603 A CN111425603 A CN 111425603A
Authority
CN
China
Prior art keywords
valve
pressure boundary
independent
valve body
integrated
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Withdrawn
Application number
CN202010339104.0A
Other languages
English (en)
Inventor
郑明光
夏栓
黄若涛
武心壮
胡波
张程
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.)
Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Original Assignee
Shanghai Nuclear Engineering Research and Design Institute 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 Shanghai Nuclear Engineering Research and Design Institute Co Ltd filed Critical Shanghai Nuclear Engineering Research and Design Institute Co Ltd
Priority to CN202010339104.0A priority Critical patent/CN111425603A/zh
Publication of CN111425603A publication Critical patent/CN111425603A/zh
Withdrawn legal-status Critical Current

Links

Images

Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
    • F16K—VALVES; TAPS; COCKS; ACTUATING-FLOATS; DEVICES FOR VENTING OR AERATING
    • F16K1/00—Lift valves or globe valves, i.e. cut-off apparatus with closure members having at least a component of their opening and closing motion perpendicular to the closing faces
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
    • F16K—VALVES; TAPS; COCKS; ACTUATING-FLOATS; DEVICES FOR VENTING OR AERATING
    • F16K1/00—Lift valves or globe valves, i.e. cut-off apparatus with closure members having at least a component of their opening and closing motion perpendicular to the closing faces
    • F16K1/32—Details
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
    • F16K—VALVES; TAPS; COCKS; ACTUATING-FLOATS; DEVICES FOR VENTING OR AERATING
    • F16K27/00—Construction of housing; Use of materials therefor
    • F16K27/02—Construction of housing; Use of materials therefor of lift valves
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/22—Structural association of coolant tubes with headers
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • Mechanical Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Valve Housings (AREA)

Abstract

本发明提出了一种一体化压力边界隔离阀，其特征在于，包括两套独立的阀体，所述阀体包括阀盖、阀瓣、阀杆及阀门操作机构，可单独操作阀瓣行程；所述一套独立阀体的出口端与所述另一套独立阀体的进口端连接有中间段，所述中间段与所述两套毒地阀体一体成型。本发明的结构取消了两道隔离阀间的连接管道，有利于简化压力边界的结构；同时取消了两道隔离阀与连接管道间的焊缝，压力边界的可靠性得到提升，也能减少在役检查时需要检测的焊缝数量；设置的两个独立的阀瓣，阀盖及阀门操作机构，便于制造，也不影响阀门原有功能的实现。

Description

一种一体化压力边界隔离阀
技术领域
本发明属于阀门领域，特别是涉及核电站反应堆冷却剂压力边界隔离阀。
背景技术
核电站中反应堆冷却剂压力边界是指在运行温度和压力下包容反应堆冷却剂和放射性物质的边界，是防止放射性裂变产物外泄的重要屏障，包括压力容器、管道、泵、阀门等。隔离阀作为反应堆冷却剂压力边界的一部分，一般用作隔离反应堆冷却剂压力边界系统和邻接系统。
根据10CFR50的要求，应设置至少两道串联的隔离阀作为反应堆冷却剂压力边界。通常情况下，两道隔离阀与设备或管道之间通过焊接的方式连接。隔离阀、设备或管道之间存在至少4道核一级焊缝。按照ASME规范的要求，电站运行时，需要定期对隔离阀、设备或管道之间的焊缝进行在役检查。焊缝的存在增加了现场施工及后续在役运行时的风险和工作量，而压力边界隔离阀通常处于高放射性区域，这也增加了人员辐照剂量。同时也增加了焊缝处冷却剂泄漏或管道破口的风险，不利于电厂的安全运行。
图1是反应堆冷却剂压力边界隔离阀的常规设置方式，两道隔离阀串联，与管道通过焊接方式连接，隔离阀之间至少两道焊缝。图2为反应堆冷却剂压力边界隔离阀的常规结构型式，由阀体、阀盖、阀瓣、阀杆等部件组成。
传统的反应堆冷却剂压力边界隔离阀设置方式，无法消除隔离阀之间的焊缝，增加了现场焊接工作及在役检查时的焊缝检查工作，增加了人员辐照剂量。同时也增加了焊缝处冷却剂泄漏或管道破口的风险，不利于电厂的安全运行。本发明设计了一种一体化的反应堆冷却剂压力边界隔离阀，通过阀体的一体化铸造，消除了传统压力边界隔离阀之间的焊缝，减少了现场施工和在役检查的工作量，消除了隔离阀之间管道破口的风险，增强了隔离阀的密封性，提高了核电站的安全性和经济性。
发明内容
本发明的目的在于提供一种一体化反应堆冷却剂压力边界隔离阀，该隔离阀用于优化反应堆冷却剂压力边界结构，提高压力边界的密封性，减少泄漏，并简化在役检查的过程，提高电站的安全性和经济性。所述一体化反应堆冷却剂压力边界隔离阀，包括两套独立的阀体，所述阀体包括阀盖、阀瓣、阀杆及阀门操作机构，可单独操作阀瓣行程；所述一套独立阀体的出口端与所述另一套独立阀体的进口端连接有中间段，所述中间段与所述两套毒地阀体一体成型。
优选的，所述中间段，便于阀门在役检查、维修和试验。
本发明提供的一体化压力边界隔离阀,用一体化铸造的隔离阀代替了原本串联的两道隔离阀。这种新型结构取消了两道隔离阀间的连接管道，有利于简化压力边界的结构；同时取消了两道隔离阀与连接管道间的焊缝，压力边界的可靠性得到提升，也能减少在役检查时需要检测的焊缝数量。此外，一体化压力边界隔离阀设置有两个独立的阀瓣，阀盖及阀门操作机构，便于制造，也不影响阀门原有功能的实现。
附图说明
图1为反应堆冷却剂压力边界隔离阀的常规设置示意图。
图2为反应堆冷却剂压力边界隔离阀的常规结构型式。
图3为本发明一体化反应堆冷却剂压力边界隔离阀示意图。
具体实施方式
为使本发明的上述目的、特征和优点能够更加明显易懂，下面结合附图和具体实施方式对本发明作进一步详细的说明。
以下结合图3对本发明进行进一步的详细说明。
一体化压力边界隔离阀主要由阀体、阀盖、阀瓣、阀杆等部件组成。其中阀体与传统阀体不同，采用两个阀体结构一体化铸造成型，同时阀体中间段适当加长，便于阀门在役检查，维修和试验。阀门设置有两个独立的阀瓣，阀盖及阀门操作机构，可单独对阀瓣进行行程操作，并可执行两个串联隔离阀的功能。
上述实施例仅例示性说明本发明的原理及其功效，而非用于限制本发明。任何熟悉此技术的人士皆可在不违背本发明的精神及范畴下，对上述实施例进行修饰或改变。因此，举凡所属技术领域中具有通常知识者在未脱离本发明所揭示的精神与技术思想下所完成的一切等效修饰或改变，仍应由本发明的权利要求所涵盖。

Claims (2)

1.一种一体化压力边界隔离阀，其特征在于，包括两套独立的阀体，所述阀体包括阀盖、阀瓣、阀杆及阀门操作机构，可单独操作阀瓣行程；所述一套独立阀体的出口端与所述另一套独立阀体的进口端连接有中间段，所述中间段与所述两套毒地阀体一体成型。
2.如权利要求1所述的一种一体化压力边界隔离阀，其特征在于，所述中间段便于阀门在役检查、维修和试验。
CN202010339104.0A 2020-04-26 2020-04-26 一种一体化压力边界隔离阀 Withdrawn CN111425603A (zh)

Priority Applications (1)

Application Number Priority Date Filing Date Title
CN202010339104.0A CN111425603A (zh) 2020-04-26 2020-04-26 一种一体化压力边界隔离阀

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CN202010339104.0A CN111425603A (zh) 2020-04-26 2020-04-26 一种一体化压力边界隔离阀

Publications (1)

Publication Number Publication Date
CN111425603A true CN111425603A (zh) 2020-07-17

Family

ID=71556821

Family Applications (1)

Application Number Title Priority Date Filing Date
CN202010339104.0A Withdrawn CN111425603A (zh) 2020-04-26 2020-04-26 一种一体化压力边界隔离阀

Country Status (1)

Country Link
CN (1) CN111425603A (zh)

Similar Documents

Publication Publication Date Title
CN106352155A (zh) 核电站一回路逆止阀带压密封检修方法
CN111425603A (zh) 一种一体化压力边界隔离阀
CN213393548U (zh) 一种一体化压力边界隔离阀
CN106644289B (zh) 一种核电站在役检查水压试验临时装置及其使用方法
Shah et al. Assessment of field experience related to pressurized water reactor primary system leaks
Roos et al. General concept for the integrity of pressurized components
Pistora et al. Evaluation of pressurised thermal shocks for VVER 440/213 reactor pressure vessel in NPP Dukovany
LI et al. RESEARCHANDAPPLICATION OF IN-SERVICE INSPECTION OF RISK-GUIDED PIPELINES IN NUCLEAR POWER PLANTS IN THE DESIGN STAGE
Murphy New Requirements for Ensuring Steam Generator Tube Integrity in Pressured Water Reactors in the United States
Svec Safety measures for NPP Mochovce-Skoda contribution
Yeong et al. Piping failure frequency analysis for the main feedwater system in domestic nuclear power plants
Koh Preliminary Evaluation of Interfacing System Loss of Coolant Accident for OPR1000
Rydlova et al. Steam and Feedwater Piping Assessment outside the Containment at Metsamor NPP
Kobayashi et al. Lessons From an Operational Small Leakage at Tsuruga Nuclear Power Station
Sharma Safety enhancement in CIRUS through ageing management and refurbishing
Plummer Reactor materials inspection by neutron radiography
Cho et al. Prospect for Seal Performance Test of the Localized APR1400’s RCP
Zhang The Important Reference Factors of Nuclear Vessel Hydrostatic Test
SHARMA Trombay, Mumbai-400 085, India; Fax:+ 91225505311; Email: sksharma@ apsara. barc. ernet. in
Haitao et al. Comparison and Reference Between RSE-M and ASME Section XI Regulations on In-Service Inspection for China Nuclear Power Plant
Beisiegel et al. Large valve test facilities of AREVA NP GmbH
JPS6229995Y2 (zh)
Lee et al. Aging assessment of Westinghouse PWR and General Electric BWR containment isolation functions
Král Evaluation of Pressurised Thermal Shocks for VVER 440/213 Reactor Pressure Vessel in NPP Dukovany (G326)
Hinovski et al. Design safety improvements of Kozloduy NPP to meet the modern safety requirements towards the old generation PWR

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
CB02 Change of applicant information

Address after: No. 29 Hong Cao Road, Xuhui District, Shanghai

Applicant after: Shanghai Nuclear Engineering Research and Design Institute Co.,Ltd.

Address before: No. 29 Hong Cao Road, Xuhui District, Shanghai

Applicant before: SHANGHAI NUCLEAR ENGINEERING RESEARCH & DESIGN INSTITUTE Co.,Ltd.

CB02 Change of applicant information
WW01 Invention patent application withdrawn after publication

Application publication date: 20200717

WW01 Invention patent application withdrawn after publication