Published 1976
| Version v1
Report
Safety conclusions from start-up tests and from the analysis of the core behaviour of Phenix
Creators
- 1. Centre d'Etudes Nucleaires de Cadarache, Saint-Paul-Lex-Durance, France
Description
The start-up tests of PHENIX and the analysis of the core behavior for more than 2 years of operation have provided substantial information for the safety analysis of similar reactors. The validity of neutronic basic data and codes is confirmed by the good prediction of the main core physical characteristics, including the neutronic feedbacks which are more specifically involved in the accident consequence evaluation. Furthermore, sodium natural convection build-up has been proved experimentally, thus improving the knowledge on its essential influence on all loss of electric supply type accidents
Additional details
Publishing Information
- Imprint Title
- Fast reactor safety and related physics. Vol. I
- Journal Page Range
- p. 61-75.
- Report number
- CONF-761001--P1
Conference
- Title
- International meeting on fast reactor safety and related physics.
- Dates
- 5 - 8 Oct 1976.
- Place
- Chicago, Illinois, USA.
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 9362882
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- PERFORMANCE; PHENIX REACTOR; REACTOR CORES; REACTOR OPERATION; REACTOR SAFETY; REACTOR START-UP
- Descriptors DEC
- BREEDER REACTORS; ENRICHED URANIUM REACTORS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; OPERATION; PLUTONIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SODIUM COOLED REACTORS