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Validation du module de thermo-hydraulique CESAR du code ASTEC V1.2 sur les expériences BETHSY


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Titre du congrès :ICONE 15th International Conference on Nuclear Engineering
Ville du congrès :Nagoya
Date du congrès :22/04/2007

Type de document > *Congrès/colloque

Mots clés > accident grave, ASTEC (code), BETHSY, CESAR, hydraulique thermique, REP

Unité de recherche > IRSN/DPAM/SEMCA/LESAM

Auteurs > BANDINI Giacomino, FLEUROT Joëlle, FOUCHER Laurent, MELONI Paride, TREGOURES Nicolas

Date de publication > 27/04/2007

Résumé

The ASTEC V1 system code is being jointly developed by the French Institut de Radioprotection et Sûreté Nucléaire (IRSN) and the German Gesellschaft für Anlagen und ReaktorSicherheit (GRS) to address severe accident sequences in a nuclear power plant. Thermal-hydraulics in primary and secondary system is addressed by the CESAR module. The aim of this paper is to present the validation of the CESAR module, from the ASTEC V1.2 version, on the basis of well instrumented and qualified integral experiments carried out in the BETHSY facility (CEA, France), which simulates a French 900 MW PWR reactor. Three tests have been thoroughly investigated with CESAR: the loss of coolant 9.1b test (OECD ISP N° 27), the loss of feedwater 5.2e test, and the multiple steam generator tube rupture 4.3b test. In the present paper, the results of the code for the three analyzed tests are presented in comparison with the experimental data. The thermal-hydraulic behavior of the BETHSY facility during the transient phase is well reproduced by CESAR: the occurrence of major events and the time evolution of main thermal-hydraulic parameters of both primary and secondary circuits are well predicted.