01679oam 2200421I 450 991070253060332120141002110127.0(CKB)5470000002428875(OCoLC)889447980(EXLCZ)99547000000242887520140828j201406 ua 0engurmn||||a||||rdacontentrdamediardacarrierResearch reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.3 /prepared by M. Dabrowski, E. StaronWashington, DC :United States Nuclear Regulatory Commission,June 2014.1 online resource (215 unnumbered pages) color illustrationsInternational agreement report ;NUREG/IA-0443Title from title screen (viewed on Aug. 28, 2014)."June 2014.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."Nuclear reactorsCoolingPolandNuclear reactorsPolandSafety measuresNuclear reactorsCoolingNuclear reactorsSafety measures.Dabrowski M.1419676Staron E.U.S. Nuclear Regulatory Commission,U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOBOOK9910702530603321Research reactor 'MARIA' primary cooling loop transient analysis using RELAP5 Mod 3.33534992UNINA