Published January 1979
| Version v1
Report
Open
Design basis accident calculation problems
Creators
- 1. CEA Centre d'Etudes Nucleaires de Saclay, 91 - Gif-sur-Yvette (France). Service d'Etudes des Reacteurs et de Mathematiques Appliquees
Description
Sudden failures of the primary circuit is the design basis accident of pressurized water reactors, being liable to affect the other two barriers separating the fission products from the environment. The calculation of the thermohydraulic behavior of the core and primary circuit is at present based, for the CEA, on the RELAP 4 code. However a second-generation code, POSEIDON, is being developed by the CEA, EDF and FRAMATOME to obtain a better description of the physical phenomena and a better estimate of safety margins. Other difficult problems arise in connection with the calculation of structural stresses and the behavior of the vessel during decompression
Availability note (English)
MF available from INIS under the Report Number.Abstract (French)
La rupture brutale du circuit primaire est l'accident de reference des reacteurs a eau sous pression; en effet, elle peut mettre en cause les deux autres barrieres qui separent les produits de fission de l'environnement. Le calcul du comportement thermohydraulique du coeur et du circuit primaire repose actuellement, pour le CEA, sur le code RELAP 4. Cependant un code de deuxieme generation, POSEIDON, est developpe par CEA, EDF et FRAMATOME pour obtenir une meilleure description des phenomenes physiques et mieux apprecier les marges de securite. D'autres problemes importants sont lies au calcul des efforts sur les structures et du comportement de l'enceinte lors de la decompressionFiles
11510767.pdf
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Additional details
Additional titles
- Original title (French)
- Les problemes de calcul de l'accident de reference
Publishing Information
- Imprint Pagination
- 21 p.
- Report number
- CEA-CONF--4539
Conference
- Title
- French-Soviet seminar on water reactor safety.
- Dates
- 10 - 17 Jan 1979.
- Place
- Saclay; Fontenay-aux-Roses, France.
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 11510767
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTER CODES; CORE FLOODING SYSTEMS; DEPRESSURIZATION; DESIGN BASIS ACCIDENTS; LOSS OF COOLANT; PRIMARY COOLANT CIRCUITS; PWR TYPE REACTORS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ECCS; REACTOR ACCIDENTS; REACTOR COMPONENTS; REACTOR COOLING SYSTEMS; REACTOR PROTECTION SYSTEMS; REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS