Article ID Journal Published Year Pages File Type
10293424 Nuclear Engineering and Design 2005 13 Pages PDF
Abstract
The AREVA realistic large break loss-of-coolant-accident (LOCA) analysis methodology received approval by the United States Nuclear Regulatory Commission (USNRC) in April 2003. The methodology references the 1988 amended 10 CFR 50.46 allowing best-estimate calculations of emergency core cooling system performance. In addition, it conforms to the code scaling, applicability, and uncertainty (CSAU) methodology developed by the Technical Program Group for the USNRC in the late 1980s; however, it also incorporates the nonparametric statistical approach originally incorporated in the Gesellschaft fur Anlagen und Reaktorsicherheit (GRS) methodology for LOCA analysis. This paper provides a methodology summary, lessons learned and insight about current LOCA issues.
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