BE853885A - Methode d'essai du dispositif de pulverisation de l'enceinte de confinement d'un reacteur nucleaire - Google Patents

Methode d'essai du dispositif de pulverisation de l'enceinte de confinement d'un reacteur nucleaire

Info

Publication number
BE853885A
BE853885A BE176955A BE176955A BE853885A BE 853885 A BE853885 A BE 853885A BE 176955 A BE176955 A BE 176955A BE 176955 A BE176955 A BE 176955A BE 853885 A BE853885 A BE 853885A
Authority
BE
Belgium
Prior art keywords
containment
nuclear reactor
spray device
test procedure
spray
Prior art date
Application number
BE176955A
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 BE853885A publication Critical patent/BE853885A/fr

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18Emergency cooling arrangements; Removing shut-down heat
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Investigating Or Analyzing Materials Using Thermal Means (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Aerodynamic Tests, Hydrodynamic Tests, Wind Tunnels, And Water Tanks (AREA)
  • Testing Of Devices, Machine Parts, Or Other Structures Thereof (AREA)
  • Investigating Materials By The Use Of Optical Means Adapted For Particular Applications (AREA)
BE176955A 1976-04-22 1977-04-22 Methode d'essai du dispositif de pulverisation de l'enceinte de confinement d'un reacteur nucleaire BE853885A (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/679,293 US4067771A (en) 1976-04-22 1976-04-22 Nuclear reactor containment spray testing system

Publications (1)

Publication Number Publication Date
BE853885A true BE853885A (fr) 1977-10-24

Family

ID=24726329

Family Applications (1)

Application Number Title Priority Date Filing Date
BE176955A BE853885A (fr) 1976-04-22 1977-04-22 Methode d'essai du dispositif de pulverisation de l'enceinte de confinement d'un reacteur nucleaire

Country Status (7)

Country Link
US (1) US4067771A (fr)
JP (1) JPS52131086A (fr)
BE (1) BE853885A (fr)
ES (1) ES457951A1 (fr)
FR (1) FR2349193A1 (fr)
GB (1) GB1524002A (fr)
IT (1) IT1080364B (fr)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2755881C3 (de) * 1977-12-15 1981-06-11 Kernforschungsanlage Jülich GmbH, 5170 Jülich Verfahren zur Abscheidung von Spalt- und Aktivierungsprodukten aus einer Gasatmosphäre und Vorrichtung z Durchführung des Verfahrens
US4395380A (en) * 1979-04-13 1983-07-26 Rosh Donald M Method of testing fluid flow condition in extension of a pipe
JPS59163594A (ja) * 1983-03-09 1984-09-14 株式会社日立製作所 緊急炉心冷却装置
CN102650604A (zh) 2011-09-26 2012-08-29 北京京东方光电科技有限公司 洁净间用气流组织测试方法及装置系统
CN103489490A (zh) * 2012-06-13 2014-01-01 中国核动力研究设计院 一种非能动安全壳喷淋装置
FR3061967B1 (fr) * 2017-01-16 2021-04-09 Aptar France Sas Procede d'analyse d'un spray genere par un dispositif de distribution de produit fluide
US11488737B2 (en) * 2019-02-15 2022-11-01 Holtec International Cooling system for casks containing high level nuclear waste
US11796255B2 (en) 2017-02-24 2023-10-24 Holtec International Air-cooled condenser with deflection limiter beams
KR102094364B1 (ko) * 2018-01-02 2020-03-27 한국수력원자력 주식회사 격납 건물의 살수 노즐 원격 진단 시스템
CN110991010B (zh) * 2019-11-13 2023-07-14 中国辐射防护研究院 一种安全壳气溶胶喷淋和自然沉降的减弱系数估算方法
CN113571214B (zh) * 2021-07-09 2024-01-23 中国核电工程有限公司 一种安全壳喷淋系统可用性试验方法
CN114689501B (zh) * 2022-02-23 2026-01-06 深圳大学 一种气溶胶冲刷模拟检测装置及其检测方法

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2816233A (en) * 1954-01-28 1957-12-10 Electronics Corp America Ice detector
US3528884A (en) * 1967-09-28 1970-09-15 Westinghouse Electric Corp Safety cooling system for a nuclear reactor
JPS5031031B1 (fr) * 1968-06-15 1975-10-06
US3736790A (en) * 1971-08-26 1973-06-05 A Pontello Apparatus for non-destructively testing fuel filters
BE788187A (fr) * 1971-09-01 1973-02-28 Babcock & Wilcox Co Systeme de proctection pour reacteurs nucleaires
US3854821A (en) * 1971-10-29 1974-12-17 Westinghouse Electric Corp Optical system for wide band light energy
US3791194A (en) * 1972-09-25 1974-02-12 Us Navy Testing of fuel filters using thermography
GB1442195A (en) * 1972-11-20 1976-07-07 Westinghouse Electric Corp Detection of leakage of fluid from nuclear reactor

Also Published As

Publication number Publication date
US4067771A (en) 1978-01-10
ES457951A1 (es) 1978-04-01
JPS52131086A (en) 1977-11-02
GB1524002A (en) 1978-09-06
FR2349193A1 (fr) 1977-11-18
JPS5720600B2 (fr) 1982-04-30
IT1080364B (it) 1985-05-16
FR2349193B1 (fr) 1983-07-01

Similar Documents

Publication Publication Date Title
FR2349193A1 (fr) Methode d'essai du dispositif de pulverisation de l'enceinte de confinement d'un reacteur nucleaire
FR2381375B1 (fr) Dispositif de support pour enceinte sous pression de reacteur nucleaire
IL55612A (en) Apparatus for the in-situ inspection of tubes while submerged in a liquid particularly of a nuclear reactor steam generator
IL54093A (en) Emergency disconnect apparatus for the manipulator arm of a nuclear reactor vessel inspection device
BE868264A (fr) Dispositif de purification du metal liquide de refroidissement du coeur d'un reacteur nucleaire a neutrons rapides
JPS56117186A (en) Motion restriction device for nuclear reactor
FR2333324A1 (fr) Reacteur nucleaire a dispositif de cloisonnement entourant le coeur
GB1540000A (en) Nuclear reactor vessel and internals alignment apparatus
IT7824411A0 (it) Complesso di taratura per apparecchi di ispezione di recipienti di reattori nucleari.
FR2507373B1 (fr) Dispositif de refroidissement de l'enceinte de confinement d'un reacteur nucleaire
JPS53112395A (en) Device for sealing up nuclear reactor vessel
DE3060228D1 (en) Sealing device for a component vertically disposed within the primary vessel of a nuclear reactor
IL55685A (en) Procedure and equipment for injecting gas into liquids such as nuclear reactor coolant
BE852829A (fr) Procede et dispositif de protection thermique de la cuve d'un reacteur nucleaire
BE830959A (fr) Dispositif de protection thermique de la cuve d'un reacteur nucleaire a neutrons rapides
JPS5374695A (en) Nuclear reactor vessel
BE865945A (fr) Dispositif de securite pour reacteur nucleaire
FR1158320A (fr) Dispositif de modification de la réactivité d'un réacteur nucléaire
BE865946A (fr) Procede et dispositif de refroidissement de la cuve d'un reacteur nucleaire a neutrons rapides
CH406453A (fr) Dispositif de refroidissement du liquide modérateur d'un réacteur nucléaire
FR2473774B1 (fr) Dispositif d'aspersion automatique de l'enceinte de confinement d'un reacteur a eau pressurisee
JPS554546A (en) Containment device of nuclear reactor apparatus
FR2550371B2 (fr) Procede et dispositif de refroidissement post-accidentel de l'enceinte de confinement d'un reacteur nucleaire
BE863804A (fr) Dispositif de protection d'une cuve suspendue de reacteur nucleaire
BE838070A (fr) Dispositif d'etancheite de tubes de passage pour thermocrupeles destine a un reacteur nucleaire

Legal Events

Date Code Title Description
RE Patent lapsed

Owner name: WESTINGHOUSE ELECTRIC CORP.

Effective date: 19920430