Westinghouse AP1000 PRA maturity

Proceedings of the American Nuclear Society - International Congress on Advances in Nuclear Power Plants 2005, ICAPP'05

Volumn 6, Issue , 2005, Pages 3354-3365

  McLaughin, D ^a   Scobel, J ^a   Schulz, T L ^a  

^a WESTINGHOUSE ELECTRIC COMPANY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ELECTRICAL POWER INDUSTRY; NUCLEAR REGULATORY COMMISSION; PASSIVE SAFETY SYSTEMS; THERMAL HYDRAULIC ANALYSIS;

ELECTRIC INDUSTRY; NUCLEAR POWER PLANTS; OPTIMIZATION; REGULATORY COMPLIANCE; SECURITY SYSTEMS;

PRESSURIZED WATER REACTORS;

EID: 34249008197     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (12)

1. Advanced Light Water Reactor Utility Requirements Document, Volume IE, ALWR Passive Plant, Revision 8, 3/99.
2. AP1000 PRA Report, Revision 5, Dec. 2003.
3. AP600 PRA Report, Revision 13, August 1998.
4. Schulz, T.L., "Risk Informing PRA Success Criteria; Application to AP1000", Proceedings of ICAPP '04, Pittsburgh, PA, USA, June 13-17, 2004
5. Handbook of Human Reliability Analysis with Emphasis on Nuclear Power Plant Applications, NUREG/CR-1278, August 1983.
6. Theofanous, T.G., et. al., "In-Vessel Coolability and Retention of a Core Melt," DOE/ID 10460, United States Department of Energy, July 1995.
7. Theofanous, T.G., et. al., "Quantification of Limits to Coolability in ULPU-2000 Configuration IV," CRSS-02/5-1, Centers for Risk Studies and Safety, University of California Santa Barbara. May 2002.
8. Dinh, T.N., et. al., "Limits of Coolability in the AP1000-Related ULPU-2400 Configuration V Facility," The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10) Seoul, Korea, October 5-9, 2003.
9. Theofanous, et. al., "Lower Head Integrity under In-Vessel Steam Explosion Loads," DOE/ID-10541, United States Department of Energy, June 1996.
10. Theofanous, T.G., Angelini, S., "Natural Convection for In-Vessel Retention at Prototypic Rayleigh Numbers," Nuclear Engineering and Design 200 (2000) 1-9.
11. ERI/NRC 03-202, Analysis of In-Vessel Retention and Ex-Vessel Fuel Coolant Interaction for AP1000, January 2004.
12. Scobel, J.H., 'The Potential for AP1000 Reactor Vessel Failure Induced by a Stratified Debris Bed with a Bottom Metal Layer during IVR, Proceedings of ICAPP-03, Cordoba, Spain, May 4-7, 2003.