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

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      Science and Technology of Nuclear Installations
      Hindawi Limited

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          Abstract

          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.

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          Determination of Sample Sizes for Setting Tolerance Limits

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            Evaluation of nuclear safety from the outputs of computer codes in the presence of uncertainties

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              Statistical aspects of best estimate method—I

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                Author and article information

                Journal
                Science and Technology of Nuclear Installations
                Science and Technology of Nuclear Installations
                Hindawi Limited
                1687-6075
                1687-6083
                2008
                2008
                : 2008
                :
                : 1-13
                Article
                10.1155/2008/239718
                c30ae68d-22ad-42b0-8f0e-cad92121116c
                © 2008

                http://creativecommons.org/licenses/by/3.0/

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