LEADER 01986oam  2200445I  450 
001 9910706113603321
005 20171018141221.0
035   $a(CKB)5470000002455295
035   $a(OCoLC)1004225229
035   $a(OCoLC)995470000002455295
035   $a(EXLCZ)995470000002455295
100   $a20170918j200207    ua             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aAnalysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP5/MOD3.2.2 gamma /$fprepared by V.A. Vinogradov, and A.Y. Balykin
210  1$aWashington, DC :$cOffice of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,$dJuly 2002.
215   $a1 online resource (various pagings) $cillustrations
225 1 $aInternational agreement report ;$vNUREG/IA-0208
300   $a"Russian Research Center 'Kurchatov Institute.' "
300   $a"July 2002."
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"Date report published: April 2002"--Bibliographic data sheet.
320   $aIncludes bibliographical references (page 48).
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
801  2$bOCLCF
801  2$bMERUC
801  2$bGPO
906   $aBOOK
912   $a9910706113603321
996   $aAnalysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP5$93485388
997   $aUNINA