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. © 2008 R. P. Martin and L. D. ODell.
Martin, R. P., & O’Dell, L. D. (2008). Development considerations of AREVA NP Inc.’s realistic LBLOCA analysis methodology. Science and Technology of Nuclear Installations, 2008. https://doi.org/10.1155/2008/239718