LEADER 01879nam  2200409I  450 
001 9910707042303321
005 20160714130426.0
035   $a(CKB)5470000002461066
035   $a(OCoLC)945968996
035   $a(OCoLC)995470000002461066
035   $a(EXLCZ)995470000002461066
100   $a20160405j201603    ua             0
101 0 $aeng
135   $aurmn||||a||||
181   $2rdacontent
182   $2rdamedia
183   $2rdacarrier
200 10$aFuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE/FRAPTRAN/Dakota codes in SNAP interface /$fprepared by Chunkuan Shih [and six others]
210  1$aWashington, DC :$cU.S. Nuclear Regulatory Commission,$dMarch 2016.
215   $a1 online resource (93 unnumbered pages) $ccolor illustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0465
300   $aTitle from title screen (viewed on Mar. 31, 2016).
300   $a"Manuscript completed: August 2015; Date published: March 2016."
300   $a"Prepared as part of The technical exchange and cooperation between the U.S. Nuclear Regulatory Commission and the Task Force for Safety Critical Software in the Field of Nuclear Safety Research."
320   $aIncludes bibliographical references (page 6-1).
606   $aNuclear power plants$zTaiwan
606   $aNuclear fuel rods$xThermal properties$xComputer programs
615  0$aNuclear power plants
615  0$aNuclear fuel rods$xThermal properties$xComputer programs.
700   $aShih$b Chunkuan$01389487
712 02$aU.S. Nuclear Regulatory Commission,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910707042303321
996   $aFuel rod performance uncertainty analysis during overpressurization transient for Kuosheng Nuclear Power Plant with TRACE$93507442
997   $aUNINA