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0346332422
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Code qualification document for best-estimate LOCA analysis
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Westinghouse Electric Corporation, Pittsburgh, PA
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0010661050
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WCAP-14449-P, Westinghouse Electric Corporation, Pittsburgh, PA
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Dederer, S.I., Tsai, C.K., Cerrone, M.B., Chyra, A., Nissley, M.E., 1995. Application of best-estimate large-break LOCA methodology to Westinghouse PWRs with upper plenum injection. WCAP-14449-P, Westinghouse Electric Corporation, Pittsburgh, PA.
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Application of Best-estimate Large-break LOCA Methodology to Westinghouse PWRs with Upper Plenum Injection
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0347593359
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WCOBRA/TRAC applicability to AP600 large-break loss-of-coolant accident
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Westinghouse Electric Corporation, Pittsburgh, PA
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Hochreiter, L.E., Kemper, R.M., Bajorek, S.M., Zhang, J., 1996. WCOBRA/TRAC applicability to AP600 large-break loss-of-coolant accident, Topic Report WCAP14171, rev. 1. Westinghouse Electric Corporation, Pittsburgh, PA.
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Hochreiter, L.E.1
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0348223154
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AP600 design certification - Thermal hydraulics testing and analysis
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Hochreiter, L.E., and Piplica, E.J., 1995. AP600 design certification - thermal hydraulics testing and analysis, Proc. NURETH-7 Conf., vol. 1, pp. 43-48.
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Hochreiter, L.E.1
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Loss-of-coolant accident performance of the Westinghouse 600-MWe advanced pressurized water reactor
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Kemper, R.M., Vertes, C.M., 1990. Loss-of-coolant accident performance of the Westinghouse 600-MWe advanced pressurized water reactor. Nucl. Technol. 91, 118-128.
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LAUR-95-4431. Los Alamos National Laboratory, Los Alamos, NM
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Lime, J.F., Boyack, B.E., 1996. Updated TRAC analysis of 80% double-ended cold leg break for the AP600, LAUR-95-4431. Los Alamos National Laboratory, Los Alamos, NM.
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Updated TRAC Analysis of 80% Double-ended Cold Leg Break for the AP600
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Lime, J.F.1
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Westinghouse advanced passive 600 plant
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McIntyre, B.A., Beck, R.K., 1992. Westinghouse advanced passive 600 plant. Nucl. Safety 33 (1), 36-46.
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0346962279
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Westinghouse code qualification document for best-estimate loss-of-coolant analysis
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WCAP-12945 (P). Letter to Westinghouse
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U.S. Nuclear Regulatory Commission (USNRC), 1996. Acceptance for referencing of the topical report, WCAP-12945 (P). Westinghouse code qualification document for best-estimate loss-of-coolant analysis, Letter to Westinghouse.
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Acceptance for Referencing of the Topical Report
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0348223151
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Loss of coolant accident resulting from a spectrum of postulated piping breaks within the reactor coolant pressure boundary
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Section 15.6.5, DE-AC03-90SF18495, rev.0-12
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Westinghouse Electric Corporation, 1992-1997. Simplified Passive Advanced Light Water Reactor Plant Program: AP600 Standard Safety Analysis Report, Section 15.6.5, Loss of coolant accident resulting from a spectrum of postulated piping breaks within the reactor coolant pressure boundary. DE-AC03-90SF18495, rev.0-12.
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WCOBRA/TRAC analysis of ORNL high flow rod bundle film boiling tests
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August 10-12, Baltimore, MD
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Zhang, J., Bajorek, S.M., Kemper, R.M., Hochreiter, L.E, 1997. WCOBRA/TRAC analysis of ORNL high flow rod bundle film boiling tests. 1997 National Heat Transfer Conf., August 10-12, Baltimore, MD.
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Acceptance criteria for emergency core cooling systems for light water nuclear power reactors, and Appendix K
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10 CFR Part 50, Section 50.46, 1992. Acceptance criteria for emergency core cooling systems for light water nuclear power reactors, and Appendix K, ECCS evaluation models.
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ECCS Evaluation Models
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