LEADER 01851oam  2200409I  450 
001 9910711783803321
005 20191209104656.0
035   $a(CKB)5470000002486230
035   $a(OCoLC)1127639953
035   $a(EXLCZ)995470000002486230
100   $a20191114j201810    ua             0
101 0 $aeng
135   $aurmn|||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aLoss of flow analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP /$fprepared by Chunkuan Shih [and six others]
210  1$aWashington, DC :$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dOctober 2018.
215   $a1 online resource (xv, 59 pages) $cillustrations (some color)
225 1 $aInternational agreement report ;$vNUREG/IA-0483
300   $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."
300   $a"Manuscript completed: May 2017; date published: October 2018."
320   $aIncludes bibliographical references (page 59).
517 3 $aLoss of flow analysis of Maanshan Nuclear Power Plant with RELAP5 Symbolic Nuclear Analysis Program
606   $aNuclear power plants$zTaiwan$xComputer programs
606   $aPressurized water reactors$xLoss of coolant
615  0$aNuclear power plants$xComputer programs.
615  0$aPressurized water reactors$xLoss of coolant.
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
906   $aBOOK
912   $a9910711783803321
996   $aLoss of flow analysis of Maanshan Nuclear Power Plant with RELAP5$93528147
997   $aUNINA