02165oam 2200517 450 991070764500332120161004122001.0(CKB)5470000002466089(OCoLC)645944149(OCoLC)301258301(EXLCZ)99547000000246608920100702j199004 ua 0engurbn||||||abptxtrdacontentcrdamediacrrdacarrierTRAC-PF1/MOD1 post-test calculations of the OECD LOFT experiment LP-SB-3 /prepared by E. J. Allen, A. P. NeillWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,April 1990.1 online resource (112 unnumbered pages) illustrationsInternational agreement report ;NUREG/IA-0022"United Kingdom Atomic Energy Authority.""April 1990.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP).""AEEW-R 2275"--Bibliographic data sheet."Technical"--Bibliographic data sheet.Includes bibliographical references (pages 14-15).TRAC PF1/MOD1 post test calculations of the OECD LOFT experiment LP-SB-3LOFT (Nuclear reactor safety test facility)ExperimentsPressurized water reactorsLoss of coolantComputer programsHydraulic transientsSimulation methodsLOFT (Nuclear reactor safety test facility)Experiments.Pressurized water reactorsLoss of coolantComputer programs.Hydraulic transientsSimulation methods.Allen E. J.1411930Neill A. P.U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,OCLCEOCLCEOCLCQOCLCOOCLCQGPOBOOK9910707645003321TRAC-PF13504177UNINA