02058oam 2200469I 450 991070356050332120150324091717.0(CKB)5470000002432095(OCoLC)905541583(OCoLC)995470000002432095(EXLCZ)99547000000243209520150324j201410 ua 0engurmn||||a||||rdacontentrdamediardacarrierPost-test thermal-hydraulic analysis of PKL tests F1.1 and F1.2 /prepared by J. Freixa [and three others] ; prepared for Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory CommissionWashington, DC :U.S. Nuclear Regulatory Commission,October 2014.1 online resource (73 unnumbered pages) color illustrationsInternational agreement report ;NUREG/IA-0417Title from title screen (viewed April 8, 2015)."Manuscript completed: April 2011 ; Date published: October 2014."Includes bibliographical references (page 7-1).Nuclear power plantsAccidentsComputer simulationNuclear power plantsComputer programsTestingPressurized water reactorsLoss of coolantComputer simulationNuclear reactor accidentsComputer simulationNuclear power plantsAccidentsComputer simulation.Nuclear power plantsComputer programsTesting.Pressurized water reactorsLoss of coolantComputer simulation.Nuclear reactor accidentsComputer simulation.Freixa J.1418374U.S. Nuclear Regulatory Commission,U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOBOOK9910703560503321Post-test thermal-hydraulic analysis of PKL tests F1.1 and F1.23529660UNINA