Published December 1975
| Version v1
Journal article
Study of the behavior of the fuel elements of water reactors in the event of a blowdown accident: the Phebus code
Creators
- 1. CEA Centre d'Etudes Nucleaires de Cadarache, 13 - Saint-Paul-les-Durance (France). Service d'Essais de Surete
Description
The programme PHEBUS was set up to study the behavior of water reactor fuel elements in the event of a depressurization hitch. Amongst other things it should allow the computing codes describing depressurization and rewetting to be ajusted for application to the calculation of power reactor accidents. It should also allow to investigate the behavior of fuel elements and the efficiency of the safety injection
Abstract (French)
Le programme PHEBUS a pour objectif d'etudier le comportement des elements combustibles des reacteurs a eau en cas d'accidents de depressurisation. Il doit, entre autres, permettre d'ajuster les codes de calcul decrivant la depressurisation et le remouillage afin de pouvoir les appliquer au calcul des accidents des reacteurs de puissance, d'etudier le comportement des elements combustibles et l'efficacite de l'injection de secoursAdditional details
Additional titles
- Original title (French)
- Etude du comportement des elements combustibles des reacteurs a eau en cas d'accident de depressurisation: programme Phebus
Publishing Information
- Journal Title
- Bull. Inf. Sci. Tech. (Paris)
- Journal Issue
- no.209
- Series
- Bull. Inf. Sci. Tech. (Paris).
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 7251692
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Descriptors DEI
- BLOWDOWN; CEA CADARACHE; ECCS; FUEL ELEMENT CLUSTERS; IN PILE LOOPS; LOSS OF COOLANT; PWR TYPE REACTORS; REACTOR SAFETY EXPERIMENTS; RESEARCH PROGRAMS; REWETTING
- Descriptors DEC
- ACCIDENTS; CEA; FRENCH ORGANIZATIONS; FUEL ASSEMBLIES; NATIONAL ORGANIZATIONS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR EXPERIMENTAL FACILITIE; REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS