LEADER 01872nam  2200409I  450 
001 9910706146303321
005 20170906095249.0
035   $a(CKB)5470000002454965
035   $a(OCoLC)1002926114
035   $a(EXLCZ)995470000002454965
100   $a20170906j200101    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aLBLOCA analysis in a Westinghouse PWR 3-loop design using RELAP5/MOD3 /$fprepared by J.I. Sa?nchez, C.A. Lage, T. Nu?n?uz
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJanuary 2001.
215   $a1 online resource (ix, 61 pages) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0195
300   $a"Empresa Nacional del Uranio S.A."
300   $a"January 2001."
300   $a"Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP)."
300   $a"Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.
320   $aIncludes bibliographical references (page 61).
606   $aPressurized water reactors$xLoss of coolant$xComputer simulation
615  0$aPressurized water reactors$xLoss of coolant$xComputer simulation.
700   $aSa?nchez$b J. I.$01411146
702   $aLage$b C. A.
702   $aNu?n?ez$b T.
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910706146303321
996   $aLBLOCA analysis in a Westinghouse PWR 3-loop design using RELAP5$93501595
997   $aUNINA