LEADER 02038nam  2200469I  450 
001 9910709689003321
005 20180521103713.0
035   $a(CKB)5470000002471343
035   $a(OCoLC)1036986293
035   $a(EXLCZ)995470000002471343
100   $a20180521j201611    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aMain steam line break analysis for Lungmen ABWR /$fprepared by Chunkuan Shih [and five others]
210  1$aWashington, DC :$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dNovember 2016.
215   $a1 online resource (xiii, 24 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0476
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: February 2016; date published: November 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 pressure vessels
606   $aBoiling water reactors
606   $aNuclear power plants$zTaiwan$xSafety measures
615  0$aNuclear fuel rods.
615  0$aNuclear pressure vessels.
615  0$aBoiling water reactors.
615  0$aNuclear power plants$xSafety measures.
700   $aShih$b Chunkuan$01389487
712 02$aU.S. Nuclear Regulatory Commission.$bDivision of Systems Analysis,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910709689003321
996   $aMain steam line break analysis for Lungmen ABWR$93505661
997   $aUNINA