ES480670A0 - Metodo para determinar si una barra de combustible de reac- tor nuclear ha sido presurizada con un gas durante su fabri-cacion. - Google Patents

Metodo para determinar si una barra de combustible de reac- tor nuclear ha sido presurizada con un gas durante su fabri-cacion.

Info

Publication number
ES480670A0
ES480670A0 ES480670A ES480670A ES480670A0 ES 480670 A0 ES480670 A0 ES 480670A0 ES 480670 A ES480670 A ES 480670A ES 480670 A ES480670 A ES 480670A ES 480670 A0 ES480670 A0 ES 480670A0
Authority
ES
Spain
Prior art keywords
pressurized
manufacture
nuclear reactor
gas during
reactor fuel
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.)
Granted
Application number
ES480670A
Other languages
English (en)
Other versions
ES8104621A1 (es
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.)
CBS Corp
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 ES8104621A1 publication Critical patent/ES8104621A1/es
Publication of ES480670A0 publication Critical patent/ES480670A0/es
Granted legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
    • 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
    • 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)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Manufacturing & Machinery (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)
ES480670A 1978-05-18 1979-05-17 Metodo para determinar si una barra de combustible de reac- tor nuclear ha sido presurizada con un gas durante su fabri-cacion. Granted ES480670A0 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US05/907,215 US4181008A (en) 1978-05-18 1978-05-18 Method of assuring nuclear fuel rod pressurization during manufacture

Publications (2)

Publication Number Publication Date
ES8104621A1 ES8104621A1 (es) 1981-03-16
ES480670A0 true ES480670A0 (es) 1981-03-16

Family

ID=25423703

Family Applications (1)

Application Number Title Priority Date Filing Date
ES480670A Granted ES480670A0 (es) 1978-05-18 1979-05-17 Metodo para determinar si una barra de combustible de reac- tor nuclear ha sido presurizada con un gas durante su fabri-cacion.

Country Status (10)

Country Link
US (1) US4181008A (es)
JP (1) JPS5827477B2 (es)
KR (1) KR820000550B1 (es)
BE (1) BE876131A (es)
ES (1) ES480670A0 (es)
FR (1) FR2426316A1 (es)
GB (1) GB2021302B (es)
IT (1) IT1114262B (es)
SE (1) SE430932B (es)
ZA (1) ZA791864B (es)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US5245640A (en) * 1992-06-02 1993-09-14 General Electric Company Nuclear fuel rod end plug pressurization hole inspection apparatus
ES2663347T3 (es) 2015-03-24 2018-04-12 Westinghouse Electric Sweden Ab Método de control de presión en una varilla de combustible
CN110189843B (zh) * 2019-06-28 2024-02-02 中机中联工程有限公司 一种核燃料组件芯块装管装置

Family Cites Families (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3504528A (en) * 1968-04-09 1970-04-07 Us Army Fluid pressure leak detector system for closed containers and the like
US3818752A (en) * 1971-04-28 1974-06-25 N Lindeberg Method and apparatus for testing tightness
JPS4889757A (es) * 1972-02-24 1973-11-22
IT974631B (it) * 1971-08-07 1974-07-10 Fukuda A Metodo per rilevare la tenuta erme tica di oggetti e dispositivo per la sua realizzazione
US4020673A (en) * 1975-01-14 1977-05-03 Exxon Nuclear Company, Inc. Fuel rod pressurization

Also Published As

Publication number Publication date
JPS54151093A (en) 1979-11-27
ES8104621A1 (es) 1981-03-16
JPS5827477B2 (ja) 1983-06-09
KR820000550B1 (ko) 1982-04-13
GB2021302B (en) 1982-06-16
BE876131A (fr) 1979-11-09
GB2021302A (en) 1979-11-28
IT7922729A0 (it) 1979-05-17
US4181008A (en) 1980-01-01
FR2426316B1 (es) 1985-03-15
FR2426316A1 (fr) 1979-12-14
ZA791864B (en) 1980-04-30
SE430932B (sv) 1983-12-19
IT1114262B (it) 1986-01-27
SE7904281L (sv) 1979-11-19

Similar Documents

Publication Publication Date Title
FR2341917A1 (fr) Faisceau combustible pour reacteur nucleaire
ES506070A0 (es) Estructura de combustible para reactor nuclear.
ES494549A0 (es) Un conjunto de combustible para un reactor nuclear
GB2031216B (en) Nuclear breeder reactor fuel element
FR2461333B1 (fr) Assemblage combustible pour reacteur a eau bouillante
GB2022310B (en) Devices for transversely holding the fuel rods of a nuclear reactor assembly
ZA776043B (en) Dismountable fuel assembly for a nuclear reactor
ES490357A0 (es) Aparato para desplazar una barra de combustible desde un re-cipiente de almacenamiento en las rejas de un conjunto de combustible para reactor nuclear
FR2421444B1 (fr) Assemblage combustible pour reacteur nucleaire
ES243076Y (es) Rejilla para conjunto de combustible de reactor nuclear.
BE876369A (fr) Assemblage combustible aisement demontable pour reacteur nucleaire
NO793707L (no) Innretning for innfoering av faste brennstoffer i en trykkforgasser-reaktor
JPS54156998A (en) Tank for storing fuel assembly for nuclear reactor
ES493288A0 (es) Metodo para producir un recipiente para combustible nuclear
IT7925891A0 (it) Perfezionamenti in gruppi combustibili per reattori nucleari.
FR2339940A1 (fr) Agencement de magasinage pour assemblages combustibles de reacteur nucleaire
BE876421A (fr) Reacteur nucleaire et element combustible associe
IT1118734B (it) Procedimento per la ricarica del combustibile in un reattore nucleare
ES280862Y (es) Barra de veneno combustible destinada a ser utilizada en un conjunto de combustible de reactor nuclear
ES511398A0 (es) Dispositivo para impedir la salida de gases de fision a traves de un agujero formado en una barra de combustible nuclear.
ES480670A0 (es) Metodo para determinar si una barra de combustible de reac- tor nuclear ha sido presurizada con un gas durante su fabri-cacion.
ES485071A0 (es) Barra de veneno combustible destinada a ser utilizada en un reactor nuclear.
ES499932A0 (es) Un metodo para formar un conducto para confinar combustible en un reactor nuclear.
FR2339232A1 (fr) Element combustible de reacteur nucleaire
ES532184A0 (es) Perfeccionamientos introducidos en una barra de combustible anular de un reactor nuclear