Published 1987
| Version v1
Book
Modelling of post-failure phenomena in LMFBR accidents
Creators
- 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France)
Description
Post-failure events in a LMFBR whole core accident such as a loss of sodium flow without scram strongly influence the reactivity evolution and the coolability of the core. Therefore, we have developed for describing these phenomena the Mocona module, which has been incorporated in the whole core accident code Physurac and validated on Cabri tests and some Capt experiments. Here we give a synthetic view of Mocona modelling and of the comparisons between calculations and experiments, some of which have been presented before. (orig.)
Additional details
Publishing Information
- Publisher
- Balkema.
- Imprint Place
- Rotterdam (Netherlands)
- ISBN
- 90-6191-764-6
- Imprint Title
- Transactions of the 9th international conference on structural mechanics in reactor technology. Vol. C
- Imprint Pagination
- 187 p.
- Journal Page Range
- p. 171-177.
Conference
- Title
- 9. biennial international conference on structural mechanics in reactor technology (SMIRT-9).
- Dates
- 17-21 Aug 1987.
- Place
- Lausanne (Switzerland).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19028877
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; FLOW RATE; FUEL PINS; HODOSCOPES; LMFBR TYPE REACTORS; LOSS OF FLOW; MOLTEN METAL-WATER REACTIONS; PRESSURE DEPENDENCE; REACTOR ACCIDENTS; SODIUM; VAPOR PRESSURE; VERIFICATION
- Descriptors DEC
- ACCIDENTS; ALKALI METALS; BREEDER REACTORS; ELEMENTS; EPITHERMAL REACTORS; FAST REACTORS; FBR TYPE REACTORS; FUEL ELEMENTS; LIQUID METAL COOLED REACTORS; METALS; PHYSICAL PROPERTIES; REACTOR COMPONENTS; REACTORS; SIMULATION; THERMODYNAMIC PROPERTIES