01603oam 2200421Ia 450 991069967480332120230902162152.0(CKB)5470000002404186(OCoLC)708256786(EXLCZ)99547000000240418620110323d2010 ua 0engurbn|||||||||txtrdacontentcrdamediacrrdacarrierRod bundle heat transfer test facility description[electronic resource] /prepared by E.R. Rosal ... [and others] ; K. Tien, NRC project managerWashington, D.C. :U.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,[2010]1 online resource (209 unnumbered pages) illustrationsTitle from PDF title screen (viewed on Mar. 23, 2011)."Manuscript completed: April 2008. Date published: July 2010.""NUREG/CR-6976."Includes bibliographical references.Pressurized water reactorsLoss of coolantNuclear fuel rodsTestingHeatTransmissionPressurized water reactorsLoss of coolant.Nuclear fuel rodsTesting.HeatTransmission.Rosal E. R1422895U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research.GPOGPOGPOBOOK9910699674803321Rod bundle heat transfer test facility description3548663UNINA