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001 9910707412703321
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100   $a20160906j201608    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aFuel rod behavior and uncertainty analysis by FRAPTRAN/TRACE/DAKOTA code in maanshan LBLOCA /$fprepared by Chunkuan Shih [and five others]
210  1$aWashington, DC:$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dAugust 2016.
215   $a1 online resource (various pagings) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0471
300   $a"Institute of Nuclear Engineering and Science, National Tsing Hua University, Nuclear and New Energy Education and Research Foundation."
300   $a"Department of Nuclear Safety, Taiwan Power Company."
300   $a"K. Tien, NRC project manager."
300   $a"Manuscript completed: March 2016; date published: August 2016."
300   $a"Prepared as part of the agreement on research participation and technical exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
320   $aIncludes bibliographical references.
606   $aNuclear fuel rods
606   $aNuclear reactor accidents$xAnalysis
606   $aPressurized water reactors$xLoss of coolant$xAnalysis
606   $aNuclear power plants$zTaiwan
615  0$aNuclear fuel rods.
615  0$aNuclear reactor accidents$xAnalysis.
615  0$aPressurized water reactors$xLoss of coolant$xAnalysis.
615  0$aNuclear power plants
700   $aShih$b Chunkuan$01389487
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis,
801  0$bGPO
801  1$bGPO
801  2$bGPO
801  2$bNKF
801  2$bCUT
801  2$bTFW
801  2$bGPO
906   $aBOOK
912   $a9910707412703321
996   $aFuel rod behavior and uncertainty analysis by FRAPTRAN$93479526
997   $aUNINA