01821nam 2200409I 450 991070583710332120170803132816.0(CKB)5470000002454048(OCoLC)999350634(EXLCZ)99547000000245404820170803j199809 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAssessment of RELAP5/MOD3.1 using LSTF ten-percent main steam-line-break test run SB-SL-01 /prepared by J.G. Oh [and seven others]Washington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,September 1998.1 online resource (viii, 111 pages) illustrationsInternational agreement report ;NUREG/IA-0148"Korea Power Engineering Company.""Korea Institute of Nuclear Safety.""Japan Atomic Energy Research Institute.""September 1998.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Maintenance Program (CAMP).""G. Rhee, NRC project manager"--Bibliographic data sheet.Includes bibliographical references (page 29).Pressurized water reactorsLoss of coolantComputer programsTestingPressurized water reactorsLoss of coolantComputer programsTesting.Oh J. G.1400314U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.Division of Systems Technology,GPOGPOBOOK9910705837103321Assessment of RELAP53466998UNINA