01876oam 2200457I 450 991070768930332120160915093850.0(CKB)5470000002465642(OCoLC)958422779(EXLCZ)99547000000246564220160915j201608 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAxial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit /prepared by William (B.J.) Marshall [and three others]Washington, DC :United States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,August 2016.1 online resource (xi, 99, A4 pages) color illustrationsTitle from title screen (viewed on Sept. 8, 2016)."NUREG/CR-7224.""ORNL/TM-2015/544.""Manuscript completed: April 2016; date published: August 2016.""Oak Ridge National Laboratory.""Mourad Aissa, NRC project manager."Includes bibliographical references (page 95-96).Boiling water reactorsSpent reactor fuelsStorageFuel burnup (Nuclear engineering)Boiling water reactors.Spent reactor fuelsStorage.Fuel burnup (Nuclear engineering)Marshall William(William B. J.),1396862U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOGPOBOOK9910707689303321Axial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit3457712UNINA