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Frepoli, C.; Petzold, J.S.; Olinski, D.C.; Chiang, J.S.
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)2010
American Nuclear Society, Inc., 555 N. Kensington Avenue, La Grange Park, Illinois 60526 (United States)2010
AbstractAbstract
[en] A complete best-estimate plus uncertainty analysis was performed to evaluate the large break loss-of-coolant accident (Design Basis Accident) for Maanshan Units 1 and 2 using Westinghouse Evaluation Model - Automated Statistical Treatment of Uncertainty Method (ASTRUM). ASTRUM follows the steps in the Code Scaling Applicability and Uncertainty (CSAU) methodology, where the 1 uncertainty analysis (Element 3 in the CSAU) is replaced by a technique based on order statistics. ASTRUM methodology received generic approval (Safety Evaluation Report) by the USNRC in 2004. ASTRUM methodology was here applied to Maanshan Units 1 and 2 and has been under review by the local Safety Authorities (Republic of China Atomic Energy Council - ROCAEC). The paper describes the development of the model, the execution of the analysis and the process utilize to assess the uncertainties. Based on the analysis assumptions, the results show compliance with the Licensing Limits for Large Break LOCAs as described in 10 CFR 50.46 (b)(1), (b)(2), and (b)(3). (authors)
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2010; 13 p; American Nuclear Society - ANS; La Grange Park, Illinois (United States); PHYSOR 2010: Advances in Reactor physics to Power the Nuclear Renaissance; Pittsburgh, PA (United States); 9-14 May 2010; ISBN 978-0-89448-079-9;
; Country of input: France; 11 refs.

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