ES8300220A1 - Procedimiento y dispositivo de inspeccion para el tratamien-to de elementos combustibles consumidos de reactor nuclear - Google Patents

Procedimiento y dispositivo de inspeccion para el tratamien-to de elementos combustibles consumidos de reactor nuclear

Info

Publication number
ES8300220A1
ES8300220A1 ES493921A ES493921A ES8300220A1 ES 8300220 A1 ES8300220 A1 ES 8300220A1 ES 493921 A ES493921 A ES 493921A ES 493921 A ES493921 A ES 493921A ES 8300220 A1 ES8300220 A1 ES 8300220A1
Authority
ES
Spain
Prior art keywords
fuel elements
inspection
deionate
deposits
nuclear 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.)
Expired
Application number
ES493921A
Other languages
English (en)
Other versions
ES493921A0 (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.)
RWE AG
Original Assignee
Rheinisch Westfaelisches Elektrizitaetswerk AG
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 Rheinisch Westfaelisches Elektrizitaetswerk AG filed Critical Rheinisch Westfaelisches Elektrizitaetswerk AG
Publication of ES493921A0 publication Critical patent/ES493921A0/es
Publication of ES8300220A1 publication Critical patent/ES8300220A1/es
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C17/00Monitoring; Testing ; Maintaining
    • G21C17/06Devices or arrangements for monitoring or testing fuel or fuel elements outside the reactor core, e.g. for burn-up, for contamination
    • G21C17/07Leak testing
    • 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)
  • Measurement Of Radiation (AREA)

Abstract

PROCEDIMIENTO Y DISPOSITIVO DE INSPECCION Y TRATAMIENTO DE ELEMENTOS COMBUSTIBLES CONSUMIDOS EN UN REACTOR NUCLEAR. CONSISTE EN LA UTILIZACION DE UN RECIPIENTE (1) RODEADO POR UN LIQUIDO, AGUA O ACIDO BORICO, QUE SE CIERRA UNA VEZ QUE SE INTRODUCEN LOS ELEMENTOS COMBUSTIBLES; SEGUIDAMENTE Y POR LOS CONDUCTOS (2) DE QUE DISPONE SE EXPULSA EL LIQUIDO MEDIANTE AIRE Y ESTE POR DESIONATO, ES DECIR AGUA DESLINIZADA Y LIBRE DE PRODUCTOS DE FISION, Y SE PROCEDE A EXTRAER POR UN CONDUCTO (5) Y LA ACCION DE UNA BOMBA (4) UNA JUESTRA CONTINUA A LA QUE SE MIDE SU ACTIVIDAD DE RADIONUCLIDOS, EN FUNCION DE LA TEMPERATURA, EN UN MEDIDOR DE ACTIVIDAD (3). CASO DE DETECTARSE UN ELEMENTO DEFECTUOSO SE RETIRA PARA TRATAMIENTO INDIVIDUAL Y EL RESTO SON TRANSFERIDOS A RECIPIENTES TRANSPORTADORES Y LLEVADOS A UN ALMACENAMIENTO INTERMEDIO O TRATAMIENTO RENOVADO. ANTES DE SER TRANSFERIDOS LOS ELEMENTOS SE CARGAN POR MEDIO DE GENERADORES DE ULTRASONIDO Y POR EL CIRCUITO FORMADO POR EL CONDUCTO (10), LA BOMBA (9) YEL SEPARADOR DE IMPUREZAS (7, 8), SE LIMPIAN DE IMPUREZAS EXTERIORES ALA VEZ QUE SE REGENERA EL DESIONATO CONTAMINADO.
ES493921A 1979-08-02 1980-08-01 Procedimiento y dispositivo de inspeccion para el tratamien-to de elementos combustibles consumidos de reactor nuclear Expired ES8300220A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE2931336A DE2931336C2 (de) 1979-08-02 1979-08-02 Verfahren zum Erkennen von Undichtigkeiten in Brennstoffumhüllungen abgebrannter Kernreaktor-Brennelemente und Inspektionsbehälter zur Durchführung des Verfahrens

Publications (2)

Publication Number Publication Date
ES493921A0 ES493921A0 (es) 1982-11-01
ES8300220A1 true ES8300220A1 (es) 1982-11-01

Family

ID=6077425

Family Applications (1)

Application Number Title Priority Date Filing Date
ES493921A Expired ES8300220A1 (es) 1979-08-02 1980-08-01 Procedimiento y dispositivo de inspeccion para el tratamien-to de elementos combustibles consumidos de reactor nuclear

Country Status (14)

Country Link
US (1) US4382906A (es)
AR (1) AR222565A1 (es)
BE (1) BE884588A (es)
BR (1) BR8004849A (es)
CA (1) CA1142654A (es)
CH (1) CH649167A5 (es)
DE (1) DE2931336C2 (es)
ES (1) ES8300220A1 (es)
FI (1) FI802415A (es)
FR (1) FR2463483B1 (es)
GB (1) GB2059139B (es)
IT (1) IT1132270B (es)
NL (1) NL8004223A (es)
SE (1) SE8005514L (es)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
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
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.

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1069791B (es) * 1959-11-26
US3073767A (en) * 1959-06-08 1963-01-15 Whitham George Kirby Reactor fuel elements testing container
GB891804A (en) * 1959-09-04 1962-03-21 Atomic Energy Authority Uk Improvements in or relating to methods of operating gas cooled nuclear reactors
DE1248822B (es) * 1965-03-31
US3375169A (en) * 1966-08-23 1968-03-26 Atomic Power Dev Ass Inc Method for minimizing corrosion of reactor elements
DE2258727A1 (de) * 1972-11-30 1974-06-06 Siemens Ag Verfahren fuer das zonenweise umsetzen von kernreaktorbrennelementen
US4034599A (en) * 1975-06-18 1977-07-12 General Electric Company Device for locating defective fuel
NL7600394A (nl) * 1976-01-15 1977-07-19 Kema Nv Werkwijze en inrichting voor het op lek controleren van een splijtstofelement.
NL7600393A (nl) * 1976-01-15 1977-07-19 Kema Nv Werkwijze en inrichting voor het op lek controleren van een splijtstofelement.
JPS52106096A (en) * 1976-03-03 1977-09-06 Hitachi Ltd Broken fuel detecting method

Also Published As

Publication number Publication date
FR2463483B1 (fr) 1985-09-13
US4382906A (en) 1983-05-10
SE8005514L (sv) 1981-02-03
NL8004223A (nl) 1981-02-04
FI802415A (fi) 1981-02-03
GB2059139A (en) 1981-04-15
FR2463483A1 (fr) 1981-02-20
ES493921A0 (es) 1982-11-01
BR8004849A (pt) 1981-02-10
DE2931336C2 (de) 1983-08-04
GB2059139B (en) 1983-02-16
CH649167A5 (de) 1985-04-30
BE884588A (fr) 1980-12-01
IT8023820A0 (it) 1980-07-31
AR222565A1 (es) 1981-05-29
DE2931336A1 (de) 1981-02-12
CA1142654A (en) 1983-03-08
IT1132270B (it) 1986-07-02

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 19971001