Published 2006
| Version v1
Book
Modeling of heat transfers inside the bottom of a PWR reactor vessel during a serious accident
Creators
- 1. CEA Cadarache (DEN/CAD/DTN/STRI), 13 - Saint Paul lez Durance (France)
- 2. CEA Grenoble (DEN/GRE/DTN/SE2T), 38 (France)
- 3. Institut de Radioprotection et de Surete Nucleaire (IRSN/DPAM/SEMCA), 13 - Saint Paul Lez Durance (France)
Description
In the framework of its studies on serious reactor accidents, the French atomic energy commission (CEA) is developing models describing the thermal behaviour of the corium (magma made of the molten core with structure materials) at the bottom of the pressure vessel, using results coming from the most recent experimental programs. This knowledge is capitalized with the scenario code ASTEC developed by IRSN and GRS. The article presents the models entered in ASTEC to calculate the heat transfers inside the corium bath and the results in terms of heat flux exchanged with the vessel. (J.S.)
Additional details
Additional titles
- Original title (French)
- Modelisation des transferts thermiques en fond de cuve au cours d'un accident grave dans un REP
Publishing Information
- Publisher
- Editions Societe Francaise de Thermique
- Imprint Place
- Paris (France)
- ISBN
- 2-905267-49-6
- Imprint Title
- Heat transfer challenges in the nuclear industry
- Imprint Pagination
- (t.1-3) 1263 p.
- Journal Page Range
- p. 1065-1070
Conference
- Title
- SFT 2006. French congress of thermal engineering. Heat transfer challenges in the nuclear industry
- Original Conference Title
- SFT 2006. Congres francais de thermique. Defis thermiques dans l'industrie nucleaire
- Dates
- 16-19 May 2006
- Place
- Ile de Re (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 38088680
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S36: MATERIALS SCIENCE; S42: ENGINEERING;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- A CODES; ABLATION; COMPUTERIZED SIMULATION; CONVECTION; CORIUM; HEAT FLUX; LAMINAR FLOW; MELTDOWN; NUSSELT NUMBER; OXIDES; PWR TYPE REACTORS; REACTOR VESSELS; STRATIFICATION; THERMAL CONDUCTION; TURBULENT FLOW
- Descriptors DEC
- ACCIDENTS; CHALCOGENIDES; COMPUTER CODES; CONTAINERS; DIMENSIONLESS NUMBERS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; FLUID FLOW; HEAT TRANSFER; MASS TRANSFER; OXYGEN COMPOUNDS; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- 9 refs. Imprint:Defis thermiques dans l'industrie nucleaire