01879nam 2200409I 450 991070704230332120160714130426.0(CKB)5470000002461066(OCoLC)945968996(OCoLC)995470000002461066(EXLCZ)99547000000246106620160405j201603 ua 0engurmn||||a||||rdacontentrdamediardacarrierFuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface /prepared by Chunkuan Shih [and six others]Washington, DC :U.S. Nuclear Regulatory Commission,March 2016.1 online resource (93 unnumbered pages) color illustrationsInternational agreement report ;NUREG/IA-0465Title from title screen (viewed on Mar. 31, 2016)."Manuscript completed: August 2015; Date published: March 2016.""Prepared as part of The technical exchange and cooperation between the U.S. Nuclear Regulatory Commission and the Task Force for Safety Critical Software in the Field of Nuclear Safety Research."Includes bibliographical references (page 6-1).Nuclear power plantsTaiwanNuclear fuel rodsThermal propertiesComputer programsNuclear power plantsNuclear fuel rodsThermal propertiesComputer programs.Shih Chunkuan1389487U.S. Nuclear Regulatory Commission,GPOGPOBOOK9910707042303321Fuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE3507442UNINA