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100   $a20160915j201608    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAxial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit /$fprepared by William (B.J.) Marshall [and three others]
210  1$aWashington, DC :$cUnited States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$dAugust 2016.
215   $a1 online resource (xi, 99, A4 pages) $ccolor illustrations
300   $aTitle from title screen (viewed on Sept. 8, 2016).
300   $a"NUREG/CR-7224."
300   $a"ORNL/TM-2015/544."
300   $a"Manuscript completed: April 2016; date published: August 2016."
300   $a"Oak Ridge National Laboratory."
300   $a"Mourad Aissa, NRC project manager."
320   $aIncludes bibliographical references (page 95-96).
606   $aBoiling water reactors
606   $aSpent reactor fuels$xStorage
606   $aFuel burnup (Nuclear engineering)
615  0$aBoiling water reactors.
615  0$aSpent reactor fuels$xStorage.
615  0$aFuel burnup (Nuclear engineering)
700   $aMarshall$b William$g(William B. J.),$01396862
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis,
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910707689303321
996   $aAxial moderator density distributions, control blade usage, and axial burnup distributions for extended BWR burnup credit$93457712
997   $aUNINA