01870oam 2200421I 450 991071199280332120191114101539.0(CKB)5470000002488160(OCoLC)1127579424(EXLCZ)99547000000248816020191114j201901 ua 0engurmn|||||||||txtrdacontentcrdamediacrrdacarrierSimulation of the LSTF-PKL Counterpart G7.1 Test at PKL facility using TRACE 5 /prepared by F. Sánchez [and three others]Washington, DC :Division of System Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission,January 2019.1 online resource (xv, 27 pages) illustrations (chiefly color)International agreement report ;NUREG/IA-0488"January 2019.""Prepared as part of The Agreement on Research Participation and Technical Exchange Under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."Includes bibliographical references (page 27).Pressurized water reactorsLoss of coolantComputer simulationNuclear power plantsAccidentsComputer simulationNuclear power plantsGermanyErlangenPressurized water reactorsLoss of coolantComputer simulation.Nuclear power plantsAccidentsComputer simulation.Nuclear power plantsSánchez-Saez Francisco1411570U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOBOOK9910711992803321Simulation of the LSTF-PKL Counterpart G7.1 Test at PKL facility using TRACE 53503157UNINA