Published July 1988 | Version v1
Journal article Metadata-only

Probabilistic analysis of PWR in-core instrumentation guide tubes wear

Creators

  • 1. Electricite de France, 75 - Paris. Direction des Etudes et Recherches

Description

This paper proposes a methodology for a component aging probabilistic analysis from feedback experience data or tests data. Three phases are described: the determination of an aging function depending on time from failures data, the evolution of the real wear from measurements performed during eddy current inspection, and the identification of parameters that have an effect on wear. This methology is applied to PWR in core instrumentation guide tubes

Abstract (French)

Cet article propose une methodologie d'analyse probabiliste du vieillissement d'un composant, a partir de donnees de retour d'experience ou de donnees d'essais. Trois etapes sont decrites: la determination d'une loi de vieillissement en fonction du temps a partir de donnees de defaillances, l'evolution de l'usure reelle a partir de mesures effectuees lors de controles par courants de Foucault, l'identification des parametres influents sur cette usure. La demarche est appliquee aux tubes d'instrumentation du coeur

Additional details

Additional titles

Original title (French)
Analyse probabiliste de l'usure des tubes d'instrumentation du coeur d'un reacteur a eau sous pression

Publishing Information

Journal Title
Bulletin de la Direction des Etudes et Recherches, Serie A
Journal Issue
no.2
Series
Bull. Dir. Etud. Rech., Ser. A.
ISSN
0013-449X
CODEN
EFDNA

INIS

Country of Publication
France
Country of Input or Organization
France
INIS RN
20003768
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
Descriptors DEI
AGE DEPENDENCE; IN CORE INSTRUMENTS; LIQUID FLOW; MECHANICAL VIBRATIONS; PWR TYPE REACTORS; WEAR
Descriptors DEC
ENRICHED URANIUM REACTORS; FLUID FLOW; POWER REACTORS; REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS