LEADER 01228nas 2200397- 450 001 9910679342703321 005 20230627152441.0 011 $a2194-4156 035 $a(OCoLC)870987699 035 $a(CKB)110978984568807 035 $a(CONSER)--2015217025 035 $a(MiAaPQ)2038911 035 $a(EXLCZ)99110978984568807 100 $a20140224a19949999 --- - 101 0 $aeng 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 00$aFinanz-Rundschau Ertragsteuerrecht $eFR : ESt - KSt - GewSt - UmwSt - ErbSt 210 1$aKöln$cSchmidt$d1994- 215 $aonline resource 311 $a1438-3292 517 3 $aFR 531 $aFINANZ RUNDSCHAU FÜR ERTRAGSTEUE 531 0 $aFinanz-Rundschau. Ertragsteuerr. (Internet) 606 $aIncome tax$xLaw and legislation$zGermany 606 $aIncome tax$xLaw and legislation$2fast$3(OCoLC)fst00968749 607 $aGermany$2fast 608 $aPeriodicals.$2fast 615 0$aIncome tax$xLaw and legislation 615 7$aIncome tax$xLaw and legislation. 676 $a343.43052 906 $aJOURNAL 912 $a9910679342703321 996 $aFinanz-Rundschau Ertragsteuerrecht$9795397 997 $aUNINA LEADER 02272oam 2200541I 450 001 9910707412703321 005 20170719110526.0 035 $a(CKB)5470000002465405 035 $a(OCoLC)957772481 035 $a(OCoLC)995470000002465405 035 $a(EXLCZ)995470000002465405 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