Safety analysis of power reactors in France: general principles and practical applications (in French)
Technical Report
·
OSTI ID:4938685
From Congress of the Society of Electrical, Electronic and Radio Engineers meeting; Vittel, France (11 Sep 1973). Before authorizing the construction or exploitation of nuclear installations, the French administration responsible for giving such authorization demands that a technical analysis of the envisaged safety equipment be carried out. The general principles used up until the present day for safety analysis of nuclear reactors are presented, examples of applications to sodium cooled fast neutron and pressurized water nuclear reactors being given. 4 references. (auth)
- Research Organization:
- CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France)
- Sponsoring Organization:
- Sponsor not identified
- NSA Number:
- NSA-29-026089
- OSTI ID:
- 4938685
- Report Number(s):
- CEA-CONF--2461; CONF-730983--1
- Country of Publication:
- France
- Language:
- French
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