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035   $a(OCoLC)793741083
035   $a(EXLCZ)995470000002409233
100   $a20120516d2011      ua             0
101 0 $aeng
135   $aurmn||||a||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 00$aFRAPTRAN 1.4$b[electronic resource] $ea computer code for the transient analysis of oxide fuel rods /$fprepared by K.J. Geelhood ... [and others]
210  1$a[Washington, DC] :$cU.S. Nuclear Regulatory Commission, Office of Nuclear Regulatory Research,$d[2011]
215   $a1 online resource (2 volumes) $ccolor illustrations ;$d28 cm
300   $a"NUREG/CR-7023."
300   $aPNNL-19400."
300   $aTitle from title screen (viewed on May 16, 2012).
320   $aIncludes bibliographical references.
517   $aFRAPTRAN 1.4 
606   $aLight water reactors$xAccidents$xComputer simulation
606   $aNuclear power plants$xAccidents$xComputer simulation
606   $aNuclear fuel rods$xPerformance$xAnalysis
615  0$aLight water reactors$xAccidents$xComputer simulation.
615  0$aNuclear power plants$xAccidents$xComputer simulation.
615  0$aNuclear fuel rods$xPerformance$xAnalysis.
701   $aGeelhood$b K. J$01390208
712 02$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   $a9910700375103321
996   $aFRAPTRAN 1.4$93543075
997   $aUNINA