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100   $a20120808d2011      ua             0
101 0 $aeng
135   $aurmn||||a||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aFRAPCON-3.4$b[electronic resource] $ea computer code for the calculation of steady state thermal-mechanical behavior of oxide fuel rods for high burnup /$fprepared by K.J. Geelhood, W.G. Luscher, C. E. Beyer
210  1$aWashington, DC :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$d[2011]
215   $a1 online resource (143 unnumbered pages) $ccolor illustrations
300   $a"Date published: March 2011."
300   $a"NUREG/CR-7022, Vol. 1."
300   $a"PNNL-19418, Vol. 1."
300   $aTitle from title screen (viewed on Aug. 8, 2012).
320   $aIncludes bibliographical references (page 4.1-4.4).
517   $aFRAPCON-3.4 
606   $aFuel burnup (Nuclear engineering)$xMathematical models$xData processing
606   $aNuclear fuel rods$xMathematical models$xData processing
606   $aNuclear fuel claddings$xMathematical models$xData processing
606   $aComputer-aided engineering
615  0$aFuel burnup (Nuclear engineering)$xMathematical models$xData processing.
615  0$aNuclear fuel rods$xMathematical models$xData processing.
615  0$aNuclear fuel claddings$xMathematical models$xData processing.
615  0$aComputer-aided engineering.
700   $aGeelhood$b K. J$01390208
701   $aLuscher$b W. G$g(Walter G.),$f1979-$01390209
701   $aBeyer$b C. E$01390210
712 02$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   $a9910700375603321
996   $aFRAPCON-3.4$93442759
997   $aUNINA