01753nam 2200409I 450 991070774010332120161110132322.0(CKB)5470000002467149(OCoLC)962368393(EXLCZ)99547000000246714920161110j199305 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierRELAP5 assessment using LSTF test data SB-CL-18 /prepared by S. Lee, B.D. Chung, H.J. KimWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,May 1993.1 online resource (xii, 206 pages) illustrationsInternational agreement report ;NUREG/IA-0095"Korea Institute of Nuclear Safety, Safety Analysis Department.""May 1993.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP).""Type of report: technical report"--Bibliographic data sheet.Includes bibliographical references (page 27).Pressurized water reactorsLoss of coolantComputer simulationPressurized water reactorsLoss of coolantComputer simulation.Lee Sukho1402929Chung B. D(Bub Dong),Kim H. J(Hho Jung),U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910707740103321RELAP5 assessment using LSTF test data SB-CL-183474446UNINA