BE904054A - Centrale electrique nucleaire - Google Patents

Centrale electrique nucleaire

Info

Publication number
BE904054A
BE904054A BE0/216145A BE216145A BE904054A BE 904054 A BE904054 A BE 904054A BE 0/216145 A BE0/216145 A BE 0/216145A BE 216145 A BE216145 A BE 216145A BE 904054 A BE904054 A BE 904054A
Authority
BE
Belgium
Prior art keywords
power plant
nuclear power
steam generator
coolant
tubes
Prior art date
Application number
BE0/216145A
Other languages
English (en)
Original Assignee
Westinghouse Electric 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 Westinghouse Electric Corp filed Critical Westinghouse Electric Corp
Publication of BE904054A publication Critical patent/BE904054A/fr

Links

Classifications

    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F22—STEAM GENERATION
    • F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
    • F22B37/00—Component parts or details of steam boilers
    • F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
    • F22B37/42—Applications, arrangements, or dispositions of alarm or automatic safety devices
    • F22B37/46—Applications, arrangements, or dispositions of alarm or automatic safety devices responsive to low or high water level, e.g. for checking, suppressing, extinguishing combustion in boilers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • 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
    • 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

Abstract

Le générateur de vapeur d'eau comporte une canalisation de décharge dans laquelle se trouve un agencement de vannes (139) normalement fermées qui s'ouvrent lorsqu'apparait une rupture dans les tubes (112) entrainant un écoulement de fluide caloporteur dans l'eau du générateur de vapeur d'eau, l'ouverture de l'agencement de vannes permettant une décharge de tout liquide en excédent dans le générateur de vapeur d'eau.
BE0/216145A 1985-01-16 1986-01-16 Centrale electrique nucleaire BE904054A (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US06/692,156 US4692297A (en) 1985-01-16 1985-01-16 Control of nuclear reactor power plant on occurrence of rupture in coolant tubes

Publications (1)

Publication Number Publication Date
BE904054A true BE904054A (fr) 1986-07-16

Family

ID=24779472

Family Applications (1)

Application Number Title Priority Date Filing Date
BE0/216145A BE904054A (fr) 1985-01-16 1986-01-16 Centrale electrique nucleaire

Country Status (7)

Country Link
US (1) US4692297A (fr)
JP (1) JPH0636057B2 (fr)
BE (1) BE904054A (fr)
CA (1) CA1264257A (fr)
FR (1) FR2576136A1 (fr)
GB (1) GB2169743B (fr)
IE (1) IE57242B1 (fr)

Families Citing this family (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS62190490A (ja) * 1986-02-18 1987-08-20 株式会社東芝 加圧水型原子力発電設備
US5309487A (en) * 1992-06-24 1994-05-03 Westinghouse Electric Corp. Mitigation of steam generator tube rupture in a pressurized water reactor with passive safety systems
US5491731A (en) * 1994-07-05 1996-02-13 Westinghouse Electric Corporation Method and system for maintaining pressure in a nuclear power plant primary loop during startup or shutdown
EP0976949B1 (fr) 1998-07-30 2002-11-27 Van Doorne's Transmissie B.V. Courroie de transmission
JP5712285B2 (ja) * 2011-04-21 2015-05-07 パフォーマンス コントラクティング，インコーポレイテッド 多重様式のデブリトラップおよび同一物を用いてデブリを分離する方法
CN103871531B (zh) * 2012-12-11 2016-08-31 中国核动力研究设计院 一种事故工况下延长蒸汽发生器满溢时间的方法
CN103050161B (zh) * 2012-12-11 2016-03-30 中国核电工程有限公司 辅助给水管线自动隔离的方法
JP2016535241A (ja) 2013-03-15 2016-11-10 ビーダブリューエックスティー エムパワー、インコーポレイテッド 長期的な原子炉冷却のための受動的技術
CN103925468A (zh) * 2014-04-21 2014-07-16 江苏赛宝龙石化有限公司 一种反应器安全控制装置
JP6429585B2 (ja) * 2014-10-20 2018-11-28 三菱重工業株式会社 原子力発電プラント及び運転方法
CN106024076B (zh) * 2016-05-18 2019-11-08 中国核电工程有限公司 一种用于降低核电厂卸压箱隔间风险的装置
CN109712733B (zh) * 2018-12-05 2020-11-06 深圳中广核工程设计有限公司 核电站蒸汽大气排放系统的安全级功能控制系统及方法
CN111540492B (zh) * 2020-05-15 2022-02-11 中国核动力研究设计院 一、二回路联动运行的综合动水腐蚀试验装置及方法
CN111627577B (zh) * 2020-06-05 2022-02-22 中国核动力研究设计院 能动设备事故环境下性能评价的试验系统及试验方法
FR3113173B1 (fr) * 2020-07-29 2022-07-29 Commissariat Energie Atomique Réacteur et Procédé de sécurité pour réacteur en cas de fusion du cœur

Family Cites Families (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3859166A (en) * 1972-12-01 1975-01-07 Combustion Eng Combined storage tank and sump for nuclear reactor
US3976541A (en) * 1974-03-18 1976-08-24 Combustion Engineering, Inc. Secondary coolant purification system with demineralizer bypass
US3989100A (en) * 1975-05-19 1976-11-02 The Babcock & Wilcox Company Industrial technique
US4113561A (en) * 1976-05-17 1978-09-12 Westinghouse Electric Corp. Valve arrangement for a nuclear plant residual heat removal system
US4104117A (en) * 1977-02-07 1978-08-01 Westinghouse Electric Corp. Nuclear reactor power generation
US4239596A (en) * 1977-12-16 1980-12-16 Combustion Engineering, Inc. Passive residual heat removal system for nuclear power plant
US4302288A (en) * 1978-10-23 1981-11-24 General Electric Company Fluid level control system
FR2487563A1 (fr) * 1980-07-25 1982-01-29 Framatome Sa Procede et dispositif de refroidissement de secours d'un reacteur nucleaire
FR2497387B1 (fr) * 1980-12-31 1985-09-06 Framatome Sa Procede et dispositif de refroidissement du circuit primaire d'un reacteur nucleaire a eau sous pression
US4424186A (en) * 1981-03-02 1984-01-03 Westinghouse Electric Corp. Power generation
DE3113803C2 (de) * 1981-04-06 1983-01-27 Kraftwerk Union AG, 4330 Mülheim Druckwasserreaktor
DE3115344A1 (de) * 1981-04-15 1982-11-04 Kraftwerk Union AG, 4330 Mülheim "kuehlung eines dampferzeugers bei einem heizrohrleck"
US4666662A (en) * 1984-07-10 1987-05-19 Westinghouse Electric Corp. Steam generator recirculating system for a pressurized water nuclear reactor

Also Published As

Publication number Publication date
CA1264257A (fr) 1990-01-09
IE57242B1 (en) 1992-06-17
FR2576136A1 (fr) 1986-07-18
JPS61167896A (ja) 1986-07-29
GB8601027D0 (en) 1986-02-19
GB2169743A (en) 1986-07-16
JPH0636057B2 (ja) 1994-05-11
US4692297A (en) 1987-09-08
GB2169743B (en) 1988-09-14
IE860010L (en) 1986-07-16

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Legal Events

Date Code Title Description
RE Patent lapsed

Owner name: WESTINGHOUSE ELECTRIC CORP.

Effective date: 19920131