CERNAVODA CANDU SEVERE ACCIDENT EVALUATION

Authors
Citation
G. Negut et A. Marin, CERNAVODA CANDU SEVERE ACCIDENT EVALUATION, Nuclear Engineering and Design, 170(1-3), 1997, pp. 67-72
Citations number
5
Categorie Soggetti
Nuclear Sciences & Tecnology
ISSN journal
00295493
Volume
170
Issue
1-3
Year of publication
1997
Pages
67 - 72
Database
ISI
SICI code
0029-5493(1997)170:1-3<67:CCSAE>2.0.ZU;2-V
Abstract
The papers present the activities dedicated to Romania Cernavoda Nucle ar Power Plant first CANDU Unit severe accident evaluation. This activ ity is part of more general PSA assessment activities. CANDU specific safety features are calandria moderator and calandria vault water capa bilities to remove the residual heat in the case of severe accidents, when the conventional heat sinks are no more available. Severe acciden ts evaluation, that is a deterministic thermal hydraulic analysis, ass esses the accidents progression and gives the milestones when importan t events take place. This kind of assessment is important to evaluate to recovery time for the reactor operators that can lead to the accide nt mitigation. The Cernavoda CANDU unit is modeled for the of all beat sinks accident and results compared with the AECL CANDU 600 assessmen t. (C) 1997 Elsevier Science S.A.