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200 10$aBias estimates used in lieu of validation of fission products and minor actinides in MCNP Keff calculations for PWR burnup credit casks /$fprepared by D.E. Mueller [and three others]
210  1$aWashington, DC :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards,$dSeptember 2015.
215   $a1 online resource (73 unnumbered pages) $ccolor illustrations
300   $a"Manuscript completed: May 2014; Date published: September 2015."
300   $aTitle from title screen (viewed on Sept. 18, 2015).
300   $a"NUREG/CR-7205."
300   $a"ORNL/TM-2012/544."
320   $aIncludes bibliographical references (page 21).
606   $aFission products$xHandling
606   $aMonte Carlo method
606   $aActinide elements
606   $aFuel burnup (Nuclear engineering)
606   $aSpent reactor fuels$xStorage
606   $aSpent reactor fuels$xTransportation
606   $aPressurized water reactors
615  0$aFission products$xHandling.
615  0$aMonte Carlo method.
615  0$aActinide elements.
615  0$aFuel burnup (Nuclear engineering)
615  0$aSpent reactor fuels$xStorage.
615  0$aSpent reactor fuels$xTransportation.
615  0$aPressurized water reactors.
700   $aMueller$b D. E.$01387026
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Material Safety and Safeguards,
712 02$aOak Ridge National Laboratory,
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