Published March 2014
| Version v1
Journal article
Gas cooled fast reactors
- 1. CEA, CEN de Saclay, 91191 Gif-sur-Yvette (France)
Description
The gas cooled fast reactor (GFR) is one of the 6 concepts selected for the 4. generation of nuclear reactors. Several GFR projects had been studied since the beginning of the sixties but the concept was given up in the eighties because of the absence of relevant advantages compared with sodium cooled fast reactors. The total absence of chemical reactivity of helium and its neutron transparency has given new assets to GFR. The article details the last GFR concept (helium cooled and carbide fuel) in terms of reactor design (particularly the fuel element) and of reactor safety. it appears that the neutronic counter-reactions are very efficient to compensate the low thermal inertia of the core in case of coolant loss. (A.C.)
Additional details
Additional titles
- Original title (French)
- Les reacteurs a neutrons rapides refroidis au gaz
Publishing Information
- Journal Title
- Revue Generale Nucleaire
- Journal Issue
- no.2
- Journal Page Range
- p. 68-76
- ISSN
- 0335-5004
- CODEN
- RGNUDJ
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 46001576
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Descriptors DEI
- FAST REACTORS; FEASIBILITY STUDIES; HELIUM COOLED REACTORS; HISTORICAL ASPECTS; MIXED CARBIDE FUELS; REACTOR CORES; REACTOR SAFETY; SPECIFICATIONS
- Descriptors DEC
- ENERGY SOURCES; EPITHERMAL REACTORS; FUELS; GAS COOLED REACTORS; MATERIALS; NUCLEAR FUELS; REACTOR COMPONENTS; REACTOR MATERIALS; REACTORS; SAFETY; SOLID FUELS
Optional Information
- Notes
- 7 refs.