LEADER 02171oam 2200505I 450 001 9910703880203321 005 20240529181230.0 035 $a(CKB)5470000002434926 035 $a(OCoLC)914301341 035 $a(EXLCZ)995470000002434926 100 $a20150723j201504 ua 0 101 0 $aeng 135 $aurmn||||a|||| 181 $2rdacontent 182 $2rdamedia 183 $2rdacarrier 200 10$aTechnical basis for peak reactivity burnup credit for BWR spent nuclear fuel in storage and transportation systems /$fprepared by William (B.J.) Marshall [and six others] 210 1$aWashington, D.C. :$cUnited States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$dApril 2015. 215 $a1 online resource (217 unnumbered pages) $ccolor illustrations 300 $aTitle from title screen (viewed on July 22, 2015). 300 $a"Manuscript completed: December 2014; Date published: April 2015." 300 $a"NUREG/CR-7194." 300 $a"ORNL/TM-2014/240." 320 $aIncludes bibliographical references (pages 125-128). 606 $aFuel burnup (Nuclear engineering) 606 $aSpent reactor fuels$xStorage$zUnited States 606 $aSpent reactor fuels$xTransportation$zUnited States 606 $aBoiling water reactors$zUnited States$xFuel$xManagement 606 $aFission products 615 0$aFuel burnup (Nuclear engineering) 615 0$aSpent reactor fuels$xStorage 615 0$aSpent reactor fuels$xTransportation 615 0$aBoiling water reactors$xFuel$xManagement. 615 0$aFission products. 700 $aMarshall$b William$g(William B. J.),$01396862 712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research, 712 02$aOak Ridge National Laboratory, 712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis and Regulatory Effectiveness, 801 0$bGPO 801 1$bGPO 801 2$bGPO 906 $aBOOK 912 $a9910703880203321 996 $aTechnical basis for peak reactivity burnup credit for BWR spent nuclear fuel in storage and transportation systems$94159550 997 $aUNINA