Published 1997 | Version v1
Book

Study of the thermohydraulic behaviour of a nuclear reactor in an accident situation

  • 1. CEA Centre d'Etudes de Cadarache, 13 - Cadarache (France). Direction des Reacteurs Nucleaires

Description

In order to assess safety criterion application, accidents in nuclear reactors are described with computation codes, and especially thermohydraulic codes; at first, evaluation codes were used, then, with the advancement of computers and physics, realistic codes such as the CATHARE code, developed by CEA, EDF and FRAMATOME, are utilized in France. CATHARE had been validated, notably with experiments on the BETHSY PWR 1/100 scaled (in volume) model, and is able to predict correctly every accidental condition. It is used for training simulations with the SIPA simulator

Part of:
50. anniversary of the CEA. Anniversary Symposium papers

Additional details

Additional titles

Original title (French)
L'etude du comportement thermohydraulique d'un reacteur nucleaire en situation accidentelle

Publishing Information

Publisher
Commissariat a l'Energie Atomique
Imprint Place
Paris (France)
ISBN
2-11-090001-6
Imprint Title
Nuclear safety
Imprint Pagination
(t.1) 263 p.
Journal Page Range
p. 213-214

Conference

Title
Symposium on nuclear safety
Original Conference Title
Colloque sur la surete nucleaire
Dates
5 Dec 1995
Place
Dijon (France)

Optional Information

Notes
Imprint:La surete nucleaire