LEADER 02081oam  2200457I  450 
001 9910711512503321
005 20191209110212.0
035   $a(CKB)5470000002484930
035   $a(OCoLC)1127640197
035   $a(EXLCZ)995470000002484930
100   $a20191114j201810    ua             0
101 0 $aeng
135   $aurmn|||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aUsing TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool /$fprepared by Jong-Rong Wang [and nine others]
210  1$aWashington, DC :$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dOctober 2018.
215   $a1 online resource (xv, 33 pages) $cillustrations (some color)
225 1 $aInternational agreement report ;$vNUREG/IA-0482
300   $a"K. Tien, NRC project manager."
300   $a"Manuscript completed: April 2017; Date published: October 2018."
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 33).
606   $aBoiling water reactors$zTaiwan$xEvaluation
606   $aNuclear power plants$zTaiwan
606   $aBoiling water reactors$zTaiwan$xComputer simulation
606   $aSpent reactor fuels$xStorage$zTaiwan
615  0$aBoiling water reactors$xEvaluation.
615  0$aNuclear power plants
615  0$aBoiling water reactors$xComputer simulation.
615  0$aSpent reactor fuels$xStorage
700   $aWang$b Jong-Rong$01397177
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis,
801  0$bGPO
801  1$bGPO
801  2$bGPO
906   $aBOOK
912   $a9910711512503321
996   $aUsing TRACE, MELCOR, CFD, and FRAPTRAN to establish the analysis methodology for Chinshan Nuclear Power Plant spent fuel pool$93462316
997   $aUNINA