LEADER 02073nam  2200529I  450 
001 9910704169803321
005 20151202093457.0
035   $a(CKB)5470000002437965
035   $a(OCoLC)930784880
035   $a(OCoLC)995470000002437965
035   $a(EXLCZ)995470000002437965
100   $a20151202j201410    ua             0
101 0 $aeng
135   $aurmn||||a||||
181   $2rdacontent
182   $2rdamedia
183   $2rdacarrier
200 10$aFRAPTRAN-1.5 /$fprepared by K.J. Geelhood, W.G. Luscher, and J.M. Cuta
210  1$aWashington, D.C. :$cUnited States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$dOctober 2014.
215   $a2 volumes $ccolor illustrations
300   $aTitle from title screen (viewed on Nov. 30, 2015).
300   $a"NUREG/CR-7023, Rev. 1."
300   $a"PNNL-19400."
300   $a"Manuscript completed: May 2014 ; Date published: October 2014."
320   $aIncludes bibliographical references.
327   $aVol. 1. A computer code for the transient analysis of oxide fuel rods -- vol. 2. Integral assessment.
606   $aNuclear fuel rods$xComputer simulation
606   $aNuclear fuel rods$xPerformance$xAnalysis
606   $aNuclear fuel rods$xData processing
606   $aNuclear fuel claddings$xData processing
606   $aNuclear power plants$xComputer simulation
615  0$aNuclear fuel rods$xComputer simulation.
615  0$aNuclear fuel rods$xPerformance$xAnalysis.
615  0$aNuclear fuel rods$xData processing.
615  0$aNuclear fuel claddings$xData processing.
615  0$aNuclear power plants$xComputer simulation.
700   $aGeelhood$b K. J.$01390208
702   $aLuscher$b W. G$g(Walter G.),$f1979-
702   $aCuta$b Judith M.
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
712 02$aPacific Northwest National Laboratory (U.S.)
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910704169803321
996   $aFRAPTRAN-1.5$93486185
997   $aUNINA