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100   $a20170918j200104    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAnalyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5/MOD3.2 and RELAP5/MOD3.2.2 GAMMA /$fprepared by V.A. Vinogradov, A.Y. Balykin
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dApril 2001.
215   $a1 online resource (various pagings) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0202
300   $a"Nuclear Reactor Institute, Russian Research Center, Kurchatov Institute."
300   $a"April 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 28).
606   $aPressurized water reactors$xLoss of coolant$xComputer simulation
615  0$aPressurized water reactors$xLoss of coolant$xComputer simulation.
700   $aVinogradov$b V. A.$0641415
702   $aBalykin$b A. Y.
712 02$aU.S. Nuclear Regulatory Commission.$bOffice of Nuclear Regulatory Research,
801  0$bGPO
801  1$bGPO
906   $aBOOK
912   $a9910706114003321
996   $aAnalyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP5$93485389
997   $aUNINA