LEADER 02284oam  2200553I  450 
001 9910706132303321
005 20180717081605.0
035   $a(CKB)5470000002455106
035   $a(OCoLC)1029057826
035   $a(EXLCZ)995470000002455106
100   $a20180320d2017      ua             0
101 0 $aeng
135   $aurbn|||||||||
181   $2rdacontent
182   $2rdamedia
183   $2rdacarrier
200 10$aEvaluation of TRACE spacer grid model with FLECHT-SEASET reflood test /$fprepared by Byung-Gil Huh, Ae-Ju Cheong, Kyung Won Lee
210  1$aWashington, D.C. :$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$d2017.
215   $a1 online resource (xiv, 131 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0481
300   $a"Manuscript completed: December 2016."
300   $a"Date published: August 2017."
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 (page 131).
517 3 $aEvaluation of TRACE spacer grid model with full-length emergency core heat transfer separate effects and systems effects test reflood test
606   $aPressurized water reactors$xLoss of coolant
606   $aNuclear fuel elements$xTesting
606   $aNuclear fuel elements$xTesting$2fast
606   $aPressurized water reactors$xLoss of coolant$2fast
608   $aOnline resources.
615  0$aPressurized water reactors$xLoss of coolant.
615  0$aNuclear fuel elements$xTesting.
615  7$aNuclear fuel elements$xTesting.
615  7$aPressurized water reactors$xLoss of coolant.
700   $aByung-Gil$b Huh$01389939
702   $aCheong$b Ae-Ju
702   $aLee$b Kyung Won
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis,
801  0$bGPO
801  1$bGPO
801  2$bGPO
801  2$bMERUC
801  2$bOCLCA
801  2$bOCLCF
801  2$bGPO
906   $aBOOK
912   $a9910706132303321
996   $aEvaluation of TRACE spacer grid model with FLECHT-SEASET reflood test$93442102
997   $aUNINA