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Reliability of a method of safety analysis (in French)

Technical Report ·
OSTI ID:4935828
;

The steps to be followed in the reliability analysis of the safety of a part of a reactor are shown. The evolution of the analysis is illustrated by an example concerning the Phenix fast neutron reactor. The steps to be followed involve the construction of logic diagrams of the reactor functioning, making clear the critical points, deflnition of accidents or incidents to be studied, examination of the material intervening in the development of the incident, optimization of the safety of the system, collection of data, and estimation of the reliability of the system for a given incident. The analysis shows the difficulties encountered in the calculation of the reliability of a protection system. (JSR)

Sponsoring Organization:
Sponsor not identified
NSA Number:
NSA-29-011994
OSTI ID:
4935828
Report Number(s):
CEA-CONF--2353; CONF-730217--4; SM--169/13
Country of Publication:
France
Language:
French

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Related Subjects

DIAGRAMS
MATHEMATICAL MODELS
N77900* --Reactors--Reactor Safety & Environmental Aspects
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTOR SAFETY
RELIABILITY