Published 1979 | Version v1
Book Metadata-only

Fast neutron reactor safety reliability analysis of Phenix decay heat removal function

Creators

  • 1. Novatome, Le Plessis-Robinson, Fr

Description

A reliability analysis of the Phenix decay heat removal function is presented. After summarizing analysis results of sequences leading to failure of this function, the main steps in a probabilistic risk assessment are described: computation of reliability and maintenance parameters for the various systems involved, followed by probabilistic analysis of failure sequences. The extent to which the various systems contribute to the total risk is analyzed. Certain maintenance recommendations were made accordingly

Additional details

Publishing Information

Publisher
American Nuclear Society.
Imprint Place
La Grange Park, IL
Imprint Title
International meeting on fast reactor safety technology
Journal Page Range
p. 2172-2182.

Conference

Title
International meeting on fast reactor safety technology.
Dates
19 - 23 Aug 1979.
Place
Seattle, WA, USA.

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
12618884
Subject category
S61: RADIATION PROTECTION AND DOSIMETRY;
Resource subtype / Literary indicator
Conference
Descriptors DEI
AFTER-HEAT REMOVAL; MAINTENANCE; PHENIX REACTOR; RELIABILITY; RISK ANALYSIS
Descriptors DEC
BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; PLUTONIUM REACTORS; POWER REACTORS; REACTORS; SODIUM COOLED REACTORS