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Science and Technology of Nuclear Installations
Volume 2008, Article ID 239718, 13 pages
Research Article

Development Considerations of AREVA NP Inc.'s Realistic LBLOCA Analysis Methodology

1AREVA NP Inc., 3315 Old Forest Road, Lynchburg, VA 24506, USA
2AREVA NP Inc., 2101 Horn Rapids Road, Richland, WA 99352, USA

Received 15 May 2007; Accepted 12 December 2007

Academic Editor: Cesare Frepoli

Copyright © 2008 Robert P. Martin and Larry D. O'Dell. This is an open access article distributed under the Creative Commons Attribution License, which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.


The AREVA NP Inc. realistic large-break loss-of-coolant-accident (LOCA) analysis methodology references the 1988 amended 10 CFR 50.46 allowing best-estimate calculations of emergency core cooling system performance. This methodology conforms to the code scaling, applicability, and uncertainty (CSAU) methodology developed by the Technical Program Group for the United States Nuclear Regulatory Commission in the late 1980s. In addition, several practical considerations were revealed with the move to a production application. This paper describes the methodology development within the CSAU framework and utility objectives, lessons learned, and insight about current LOCA issues.