01725oam 2200445Ia 450 991070150470332120120419105521.0(CKB)5470000002420046(OCoLC)786165454(EXLCZ)99547000000242004620120419d2012 ua 0engurcn|||||||||txtrdacontentcrdamediacrrdacarrierPost-test calculation of the ROSA/LSTF test 3-2 using RELAP5/Mod3.3[electronic resource] /prepared by V. Martinez, F. Reventós, C. PretelWashington, DC :U.S. Nuclear Regulatory Commission,[2012]1 online resource (45 unnumbered pages) color illustrationsInternational agreement report ;NUREG/IA-04010"Date published: March 2012."Title from title screen (viewed on Apr. 19, 2012).Includes bibliographical references (pages 7-1).Pressurized water reactorsLoss of coolantComputer simulationNuclear power plantsAccidentsComputer simulationNuclear power plantsComputer programsPressurized water reactorsLoss of coolantComputer simulation.Nuclear power plantsAccidentsComputer simulation.Nuclear power plantsComputer programs.Martinez V1405889Reventós F1387562Pretel C1405890U.S. Nuclear Regulatory Commission.GPOGPOGPOBOOK9910701504703321Post-test calculation of the ROSA3483278UNINA