02045nam 2200397I 450 991070611400332120170918080806.0(CKB)5470000002455291(OCoLC)1004224928(EXLCZ)99547000000245529120170918j200104 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAnalyses 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 /prepared by V.A. Vinogradov, A.Y. BalykinWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,April 2001.1 online resource (various pagings) illustrationsInternational agreement report ;NUREG/IA-0202"Nuclear Reactor Institute, Russian Research Center, Kurchatov Institute.""April 2001.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Code Application and Maintenance Program (CAMP).""Sponsoring organization: Division of Systems Analysis and Regulatory Effectiveness, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission"--Bibliographic data sheet.Includes bibliographical references (page 28).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,GPOGPOBOOK9910706114003321Analyses of KS test data on the heated rod bundle temperature behavior in RBMK-1500 core model under stop and recovery flow using RELAP53485389UNINA