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001 9910703833003321
005 20151203082819.0
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035   $a(OCoLC)930865214
035   $a(OCoLC)995470000002435403
035   $a(EXLCZ)995470000002435403
100   $a20151203j201410    ua             0
101 0 $aeng
135   $aurmn||||a||||
181   $2rdacontent
182   $2rdamedia
183   $2rdacarrier
200 10$aFRAPCON-3.5 /$fprepared by K.J. Geelhood and W.G. Luscher
210  1$aWashington, DC :$cUnited States Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$dOctober 2014.
215   $a1 online resource (2 volumes) $ccolor illustrations
300   $aTitle from title screen (viewed on Nov. 27, 2015).
300   $a"Manuscript completed: May 2014 ; Date published: October 2014."
300   $a"NUREG/CR-7024, Rev. 1."
300   $a"PNNL-19418, Rev. 1."
320   $aIncludes bibliographical references.
327   $av. 1. A computer code for the calculation of steady-state, thermal-mechanical behavior of oxide fuel rods for high burnup -- v. 2. Integral assessment.
606   $aNuclear fuel rods$xData processing
606   $aNuclear fuel claddings$xData processing
606   $aNuclear fuel rods$xComputer simulation
606   $aNuclear fuel rods$xComputer programs
606   $aNuclear power plants$xAccidents$xComputer simulation
606   $aLight water reactors$xAccidents$xComputer simulation
615  0$aNuclear fuel rods$xData processing.
615  0$aNuclear fuel claddings$xData processing.
615  0$aNuclear fuel rods$xComputer simulation.
615  0$aNuclear fuel rods$xComputer programs.
615  0$aNuclear power plants$xAccidents$xComputer simulation.
615  0$aLight water reactors$xAccidents$xComputer simulation.
700   $aGeelhood$b K. J.$01390208
702   $aLuscher$b W. G$g(Walter G.),$f1979-
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$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910703833003321
996   $aFRAPCON-3.5$93503061
997   $aUNINA