LEADER 02005nam  2200433I  450 
001 9910708659703321
005 20170406072736.0
035   $a(CKB)5470000002470628
035   $a(OCoLC)981756112
035   $a(EXLCZ)995470000002470628
100   $a20170406j201606    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aMain stream line break analysis for lungmen ABWR /$fprepared by Chunkuan Shih [and five others]
210  1$aWashington, DC :$cDivision of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJune 2016.
215   $a1 online resource (xiii, 24 pages) $cillustrations$e+ errata
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)."
300   $a"Correct 'manuscript completed date' to read 'June 2016' "--Errata.
320   $aIncludes bibliographical references (page 23).
606   $aNuclear reactor accidents$xComputer simulation
606   $aNuclear fuel rods$xTesting
615  0$aNuclear reactor accidents$xComputer simulation.
615  0$aNuclear fuel rods$xTesting.
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   $a9910708659703321
996   $aMain stream line break analysis for lungmen ABWR$93520305
997   $aUNINA