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100   $a20100416d2009      ua             0
101 0 $aeng
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181   $ctxt$2rdacontent
182   $cc$2rdamedia
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200 00$aDevelopment and testing of ENDF/B-VI.8 and ENDF/B-VII.0 coupled neutron-gamma libraries for SCALE 6$b[electronic resource] /$fprepared by D. Wiarda ... [and others]
210  1$aWashington, DC :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Material Safety and Safeguards,$d[2009]
215   $a1 online resource (140 pages) $cillustrations (chiefly color)
300   $aTitle from PDF title screen (viewed on Apr. 16, 2010).
300   $a"Date published: February 2009."
300   $aPerforming organization: Oak Ridge National Laboratory.
300   $a"NUREG/CR-6990."
300   $a"ORNL/TM-2008/047."
320   $aIncludes bibliographical references (pages 89-90).
606   $aCriticality (Nuclear engineering)
606   $aNuclear power plants$zUnited States$xShielding (Radiation)$xData processing
606   $aNuclear power plants$zUnited States$xShielding (Radiation)$xComputer programs
606   $aNuclear reactors$zUnited States$xShielding (Radiation)$xData processing
606   $aNuclear reactors$zUnited States$xShielding (Radiation)$xComputer programs
606   $aNeutron cross section standards$vDatabases
606   $aNeutron cross section standards$xComputer programs
615  0$aCriticality (Nuclear engineering)
615  0$aNuclear power plants$xShielding (Radiation)$xData processing.
615  0$aNuclear power plants$xShielding (Radiation)$xComputer programs.
615  0$aNuclear reactors$xShielding (Radiation)$xData processing.
615  0$aNuclear reactors$xShielding (Radiation)$xComputer programs.
615  0$aNeutron cross section standards
615  0$aNeutron cross section standards$xComputer programs.
701   $aWiarda$b Dorothea$01420780
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Material Safety and Safeguards.
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Spent Fuel Storage and Transportation.
712 02$aOak Ridge National Laboratory.
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910699100403321
996   $aDevelopment and testing of ENDF$93539853
997   $aUNINA

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