European Pressurized water Reactor (EPR) SAR ATWS Accident Analyses by using 3D Code Internal Coupling Method
Conference
·
OSTI ID:21160687
- Framatome ANP, Tour Areva - 1, place de la Coupole - 92084 Paris La Defense (France)
- Framatome ANP, Lynchburg - 3315 Old Forest Road, Lynchburg, VA 24501 (United States)
Anticipated Transients Without Scram (ATWS) accident analyses make part of the Safety Analysis Report of the European Pressurized water Reactor (EPR), covering Risk Reduction Category A (Core Melt Prevention) events. This paper deals with three of the most penalizing RRC-A sequences of ATWS caused by mechanical blockage of the control/shutdown rods, regarding their consequences on the Reactor Coolant System (RCS) and core integrity. A new 3D code internal coupling calculation method has been introduced. (authors)
- Research Organization:
- American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
- OSTI ID:
- 21160687
- Country of Publication:
- United States
- Language:
- English
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