Published January 1976 | Version v1
Journal article Metadata-only

Safety studies on oxide fuel elements for the fast neutron programme

Creators

  • 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Service de Developpement et d'Essais d'Elements Combustibles

Description

Studies leading to the definition of a fuel element and instructions for its use overlap with safety studies to the extent that they must guarantee, for nominal running conditions, a failure rate consistent with the working rules of the Station. Given the present state of knowledge on the causes and kinetics of damage affecting the cladding, it is mainly dealt with the principles of this research. The advantages of applying statistical computing methods to the two factors which govern the lifetime of the pins: their working conditions and quality, are demonstrated

Abstract (French)

Les etudes qui aboutissent a la definition d'un element combustible et a ses consignes d'utilisation recoupent les etudes de surete dans la mesure ou elles doivent garantir, pour les conditions nominales de fonctionnement, un taux de defaillance compatible avec les regles d'exploitation de la Centrale. En l'etat actuel des connaissances sur les causes et la cinetique de dommages qui affectent la gaine, ce sont essentiellement les principes de ces etudes qui sont exposes ici. On montre l'interet d'appliquer les methodes de calcul statistique aux deux facteurs qui conditionnent la duree de vie des aiguilles: leurs conditions de fonctionnement et leur qualite

Additional details

Additional titles

Original title (French)
Surete des elements combustibles a oxyde de la filiere a neutrons rapides

Publishing Information

Journal Title
Bull. Inf. Sci. Tech. (Paris)
Journal Issue
no.210
Series
Bull. Inf. Sci. Tech. (Paris).

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
7251774
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
CREEP; FUEL CANS; FUEL ELEMENT FAILURE; FUEL PINS; LMFBR TYPE REACTORS; NUCLEAR POWER PLANTS; PHENIX REACTOR; PHYSICAL RADIATION EFFECTS; PLUTONIUM OXIDES; RELIABILITY; RUPTURES; URANIUM OXIDES
Descriptors DEC
ACCIDENTS; ACTINIDE COMPOUNDS; BREEDER REACTORS; CHALCOGENIDES; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; MECHANICAL PROPERTIES; NUCLEAR FACILITIES; OXIDES; OXYGEN COMPOUNDS; PLUTONIUM COMPOUNDS; PLUTONIUM REACTORS; POWER PLANTS; POWER REACTORS; RADIATION EFFECTS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTORS; SODIUM COOLED REACTORS; THERMAL POWER PLANTS; TRANSURANIUM COMPOUNDS; URANIUM COMPOUNDS