Need of a coherent and consistent Phenomena Identification and Ranking Table (PIRT) to address small, intermediate and large break LOCA in PWRs

Transactions of the American Nuclear Society

Volumn 95, Issue , 2006, Pages 654-656

  Frepoli, Cesare ^a  

^a WESTINGHOUSE ELECTRIC COMPANY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 33845540889     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (8)

1. Boyack, B. E., et al., 1989, "Quantifying Reactor Safety Margins," NUREG/CR-5249.
2. Bajorek, S.M, Ginsberg, A, Shimeck, D.J., Ohkawa, K., Young, M.Y, Hochreiter, L.E., Griffith, P., Hassan, Y., Fernandez, T., Speyer, D., "Small Break Loss of Coolant Accident Phenomena Identification and Ranking Table (PIRT) for Westinghouse Pressurized Water Reactors," Ninth International Topical Meeting on Nuclear Reactor Theraml Hydraulic (NURETH-9), San Francisco, October 3-8, 1999.
3. th International Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, October 4-8, 2004.
4. th International Topical Meeting on Nuclear Reactor Thermal-Hydraulics (NURETH-11), Avignon, France, October 2-6, 2005.
5. Muftuoglu, K., Ohkawa, K., Frepoli, C., Nissley, M.E., 2004, "Comparison of Realistic Large Break LOCA Analyses of a 3-Loop Westinghouse Plant Using Response Surface and Statistical Sampling Techniques," Proceedings of ICONE-12, International Conference on Nuclear Engineering. April 25-29, 2004, Arlington, Virginia (Washington D.C.), U.S.A.
6. Nissley, M. E., Frepoli, C., Ohkawa, K., and Muftuoglu, K., 2005, "Realistic Large-Break LOCA Evaluation Methodology Using the Automated Statistical Treatment of Uncertainty Method (ASTRUM)," Technical Report WCAP-16009-NP-A, Westinghouse Electric Company, Pittsburgh, PA.
7. Takeuchi, K. and Nissley, M. E., 2000, "Best Estimate Loss-of-Coolant Accident Licensing Methodology Based on WCOBRA/TRAC Code," Methods in Nucl. Installation Safety Analysis (BE-2000) Washington D.C., November 2000
8. Young, M. Y., Bajorek, S. M., Nissley, M. E., and Hochreiter, L. E., 1998, "Application of code scaling applicability and uncertainty methodology to the large break loss of coolant," Nuclear Engineering and Design 186 (1998) 39-52