01905oam 2200433I 450 991071190530332120191120143749.0(CKB)5470000002489044(OCoLC)1128097666(EXLCZ)99547000000248904420191120j201902 ua 0engurmn|||||||||txtrdacontentcrdamediacrrdacarrierPost-test calculation of the PKL-2 test G7.1 using RELAP5/MOD3.3 /prepared by V. Martinez-Quiroga, F. Reventos, C. PretelWashington, DC :Division of Systems Analysis, Office of Nuclear Regulatory Research, Nuclear Regulatory Commission,February 2019.1 online resource (xv, 17 pages) illustrations (chiefly color)International agreement report ;NUREG/IA-0499"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP).""Kirk Tien, NRC project manager.""Manuscript completed: November 2017; Date published: February 2019."Includes bibliographical references (page 17).Pressurized water reactorsAccidentsComputer simulationNuclear power plantsAccidentsComputer programsPressurized water reactorsAccidentsComputer simulation.Nuclear power plantsAccidentsComputer programs.Martínez-Quiroga Victor1408347Reventós F.Pretel C.U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOBOOK9910711905303321Post-test calculation of the PKL-2 test G7.1 using RELAP53491980UNINA