Published 1990
| Version v1
Book
Thermomechanical model in the SURFASS code for hexcan distortion and rupture
- 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France). Dept. de Protection
- 2. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-lez-Durance (France)
Description
Some thermomechanical models have been implement in the SURFASS code to account for the distortion and failure of a fast reactor subassembly hexcan during a Total Instantaneous Blockage accident. SURFASS calculations show that the hexcan distortions increase the heat transfer between the neighbouring hexcans, and therefore the output sodium temperature in the next one. The failure models will have to be validated with the help of the COTHAA experiments. (author)
Additional details
Additional titles
- Augmented title (English)
- In fast reactor fuel assemblies
Publishing Information
- Publisher
- British Nuclear Energy Society.
- Imprint Place
- London (United Kingdom)
- ISBN
- 0 7277 1566 6
- Imprint Title
- Fast reactor core and fuel structural behaviour
- Imprint Pagination
- 326 p.
- Journal Page Range
- p. 97-104.
Conference
- Title
- International conference on fast reactor core and fuel structural behaviour.
- Dates
- 4-6 Jun 1990.
- Place
- Inverness (United Kingdom).
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- United Kingdom
- INIS RN
- 23049256
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; DEFORMATION; FLOW BLOCKAGE; FUEL ASSEMBLIES; HEAT TRANSFER; HEXAGONAL CONFIGURATION; LMFBR TYPE REACTORS; RUPTURES; S CODES; TUBES; VERIFICATION
- Descriptors DEC
- BREEDER REACTORS; COMPUTER CODES; CONFIGURATION; ENERGY TRANSFER; EPITHERMAL REACTORS; FAILURES; FAST REACTORS; FBR TYPE REACTORS; LIQUID METAL COOLED REACTORS; REACTORS; SIMULATION