Published 1988
| Version v1
Book
Safety studies performed with Cathare code: loss of coolant accident with delayed reactor coolant pump trip and main steamline break studies
Creators
- 1. Electricite de France, 75 - Paris
- 2. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-Lez-Durance (France)
Description
Developed and assessed by a joint team of 20 people from EDF, CEA and FRAMATOME located in Grenoble (see dedicated presentations during the same meeting), the French Advanced Code CATHARE is industrially used at EDF/SEPTEN since 1984 to perform PWR safety studies. The two examples developed hereafter have been selected to show the industrial approach of using CATHARE at EDF/SEPTEN to perform safety studies. These examples will also demonstrate the great capability of CATHARE to allow the improvement of the methodology used to perform studies of main steamline breaks. This advanced methodology is developed through a joint action EDF/SEPTEN and CEA/SCOS
Additional details
Additional titles
- Original title (no language)
- Actes de la Conference Internationale ENS/ANS sur la surete des reacteurs thermiques. Volume 1.
Publishing Information
- Publisher
- Societe Francaise d'Energie Nucleaire.
- Imprint Place
- Paris (France)
- Imprint Title
- Proceedings of the International ENS/ANS Conference on thermal reactor safety. Volume 1
- Imprint Pagination
- 417 p.
- Journal Page Range
- p. 109-116.
Conference
- Title
- International ENS/ANS Conference on thermal reactor safety.
- Dates
- 2-7 Oct 1988.
- Place
- Avignon (France).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 21015088
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- C CODES; HYDRAULICS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY; RUPTURES; STEAM LINES; THERMODYNAMICS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENRICHED URANIUM REACTORS; FAILURES; PIPELINES; POWER REACTORS; REACTOR ACCIDENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Notes
- Imprint:Actes de la Conference Internationale ENS/ANS sur la surete des reacteurs thermiques. Volume 1.