02275oam 2200553 450 991070383300332120151203082819.0(CKB)5470000002435403(OCoLC)930865214(OCoLC)995470000002435403(EXLCZ)99547000000243540320151203j201410 ua 0engurmn||||a||||rdacontentrdamediardacarrierFRAPCON-3.5 /prepared by K.J. Geelhood and W.G. LuscherWashington, DC :United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,October 2014.1 online resource (2 volumes) color illustrationsTitle from title screen (viewed on Nov. 27, 2015)."Manuscript completed: May 2014 ; Date published: October 2014.""NUREG/CR-7024, Rev. 1.""PNNL-19418, Rev. 1."Includes bibliographical references.v. 1. A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup -- v. 2. Integral assessment.Nuclear fuel rodsData processingNuclear fuel claddingsData processingNuclear fuel rodsComputer simulationNuclear fuel rodsComputer programsNuclear power plantsAccidentsComputer simulationLight water reactorsAccidentsComputer simulationNuclear fuel rodsData processing.Nuclear fuel claddingsData processing.Nuclear fuel rodsComputer simulation.Nuclear fuel rodsComputer programs.Nuclear power plantsAccidentsComputer simulation.Light water reactorsAccidentsComputer simulation.Geelhood K. J.1390208Luscher W. G(Walter G.),1979-U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,Pacific Northwest National Laboratory (U.S.)GPOGPOGPOBOOK9910703833003321FRAPCON-3.53503061UNINA