01986oam 2200445I 450 991070611360332120171018141221.0(CKB)5470000002455295(OCoLC)1004225229(OCoLC)995470000002455295(EXLCZ)99547000000245529520170918j200207 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAnalysis 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 /prepared by V.A. Vinogradov, and A.Y. BalykinWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,July 2002.1 online resource (various pagings) illustrationsInternational agreement report ;NUREG/IA-0208"Russian Research Center 'Kurchatov Institute.' ""July 2002.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP).""Date report published: April 2002"--Bibliographic data sheet.Includes bibliographical references (page 48).Pressurized water reactorsLoss of coolantComputer simulationPressurized water reactorsLoss of coolantComputer simulation.Vinogradov V. A.641415Balykin A. Y.U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOOCLCFMERUCGPOBOOK9910706113603321Analysis of the VTI test data on the behavior of the heated rod temperatures in the partially uncovered VVER-440 core model using RELAP53485388UNINA