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BE866560A - Cellule de ressuage pour le controle de l'etancheite d'assemblages d'elements combustibles et procede de controle correspondant - Google Patents

Cellule de ressuage pour le controle de l'etancheite d'assemblages d'elements combustibles et procede de controle correspondant

Info

Publication number
BE866560A
BE866560A BE187268A BE187268A BE866560A BE 866560 A BE866560 A BE 866560A BE 187268 A BE187268 A BE 187268A BE 187268 A BE187268 A BE 187268A BE 866560 A BE866560 A BE 866560A
Authority
BE
Belgium
Prior art keywords
checking
sealing
check process
corresponding check
element assemblies
Prior art date
Application number
BE187268A
Other languages
English (en)
Original Assignee
Framatome Sa
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 Framatome Sa filed Critical Framatome Sa
Publication of BE866560A publication Critical patent/BE866560A/fr

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/06—Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/07—Leak testing
    • 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

  • 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)
  • Fuel Cell (AREA)
BE187268A 1977-04-29 1978-04-28 Cellule de ressuage pour le controle de l'etancheite d'assemblages d'elements combustibles et procede de controle correspondant BE866560A (fr)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7712938A FR2389202A1 (fr) 1977-04-29 1977-04-29 Cellule de ressuage pour le controle de l'etancheite d'assemblages d'elements combustibles et procede de controle correspondant

Publications (1)

Publication Number Publication Date
BE866560A true BE866560A (fr) 1978-10-30

Family

ID=9190068

Family Applications (1)

Application Number Title Priority Date Filing Date
BE187268A BE866560A (fr) 1977-04-29 1978-04-28 Cellule de ressuage pour le controle de l'etancheite d'assemblages d'elements combustibles et procede de controle correspondant

Country Status (9)

Country Link
US (1) US4225388A (fr)
JP (1) JPS5851240B2 (fr)
BE (1) BE866560A (fr)
DE (1) DE2818900C2 (fr)
ES (1) ES468616A1 (fr)
FR (1) FR2389202A1 (fr)
GB (1) GB1594522A (fr)
NL (1) NL182597C (fr)
ZA (1) ZA782124B (fr)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2461337A1 (fr) * 1979-07-06 1981-01-30 Centre Etd Energie Nucleaire Methode de localisation d'un barreau fuyard dans un assemblage de combustible nucleaire
FR2466082A1 (fr) * 1979-09-26 1981-03-27 Framatome Sa Procede de detection acoustique et ultrasonique d'assemblages combustibles d'un reacteur nucleaire devenus defectueux en service et dispositif de detection correspondant
JPS58134797U (ja) * 1982-03-05 1983-09-10 原子燃料工業株式会社 シツピング装置におけるシツピングキャン
US4643866A (en) * 1983-08-24 1987-02-17 The Babcock & Wilcox Company Nuclear fuel pellet-cladding interaction test device and method modeling in-core reactor thermal conditions
FR2569041B1 (fr) * 1984-08-08 1987-01-02 Fragema Framatome & Cogema Procede et dispositif de controle par ressuage de l'etancheite des gaines d'un assemblage de combustible nucleaire
US4659536A (en) * 1985-06-14 1987-04-21 Proto-Power Corporation System and method for consolidating spent fuel rods
FR2666924B1 (fr) * 1990-09-13 1992-12-18 Framatome Sa Procede et dispositif de detection de fuite sur un element combustible d'un assemblage pour reacteur nucleaire.
US5754610A (en) * 1996-12-05 1998-05-19 Framatome Technologies, Inc. In-mast sipping modular mast modification
CN117129152B (zh) * 2023-10-26 2024-02-09 合肥中航天成电子科技有限公司 一种壳体气密性测试设备

Family Cites Families (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE7303327U (de) * 1974-09-05 Interatom Gmbh Vorrichtung zur Überprüfung von Brennelementen flüssigkeitsgekühlter Kernreaktoren auf Hüllrohrschäden
FR1375685A (fr) * 1961-07-29 1964-10-23 Siemens Ag Dispositif pour la permutation axiale des éléments combustibles d'un réacteur nucléaire
FR1328935A (fr) * 1962-02-23 1963-06-07 Grenobloise Etude Appl Perfectionnements aux dispositifs de détection des ruptures de gaine dans les réacteurs atomiques
DE1248822B (fr) * 1965-03-31
US3801441A (en) * 1971-10-12 1974-04-02 Transfer Systems Failed nuclear reactor fuel detection apparatus
FR2202341B1 (fr) * 1972-10-09 1976-11-19 Aristarkhov Nikolai
DE2258727A1 (de) * 1972-11-30 1974-06-06 Siemens Ag Verfahren fuer das zonenweise umsetzen von kernreaktorbrennelementen
US3947318A (en) * 1973-12-17 1976-03-30 Ivan Ilich Zhuchkov Liquid-metal-cooled reactor
AT348073B (de) * 1974-05-20 1979-01-25 Babcock Brown Boveri Reaktor Verfahren und vorrichtung zum lokalisieren defekter brennstaebe wassergekuehlter kern- reaktoren
US4039376A (en) * 1974-06-24 1977-08-02 Wachter William J Method and apparatus for inspection of nuclear fuel rods
US4034599A (en) * 1975-06-18 1977-07-12 General Electric Company Device for locating defective fuel
US4082607A (en) * 1976-09-30 1978-04-04 The United States Of America As Represented By The United States Department Of Energy Fuel subassembly leak test chamber for a nuclear reactor
JPS5512078A (en) * 1978-07-14 1980-01-28 Nichiban Kk Device for seallup with tape

Also Published As

Publication number Publication date
US4225388A (en) 1980-09-30
ES468616A1 (es) 1979-04-01
ZA782124B (en) 1979-03-28
JPS5851240B2 (ja) 1983-11-15
DE2818900A1 (de) 1978-11-02
FR2389202A1 (fr) 1978-11-24
GB1594522A (en) 1981-07-30
NL7802647A (nl) 1978-10-31
DE2818900C2 (de) 1988-12-22
NL182597C (nl) 1988-04-05
JPS53136193A (en) 1978-11-28
FR2389202B1 (fr) 1981-04-17
NL182597B (nl) 1987-11-02

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Legal Events

Date Code Title Description
RE20 Patent expired

Owner name: SOC. FRANCO-AMERICAINE DE CONSTRUCTIONS ATOMIQUES

Effective date: 19980428