01704nam 2200397I 450 991070582900332120170807101057.0(CKB)5470000002454129(OCoLC)999728150(EXLCZ)99547000000245412920170807j199808 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAssessment of RELAP5/MOD3.2 using LOFT large break LOCA test, LP-02-6 /prepared by T.S. Choi [and seven others]Washington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,August 1998.1 online resource (vi, 68, A38 pages) illustrationsInternational agreement report ;NUREG/IA-0139"Korea Nuclear Fuel Company.""Korea Institute of Nuclear Safety, Advanced Reactor Dept.""August 1998.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP).""S. Smith, NRC project manager"--Bibliographic data sheet.Includes bibliographical references.Pressurized water reactorsLoss of coolantComputer simulationPressurized water reactorsLoss of coolantComputer simulation.Choi T. S.1416616U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910705829003321Assessment of RELAP53522561UNINA