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

  • 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

Part of:
Proceedings of the international ENS/ANS conference on thermal reactor safety. Volume 1

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.