02025nam 2200433I 450 991070778220332120161028131434.0(CKB)5470000002466723(OCoLC)961353979(EXLCZ)99547000000246672320161028j199206 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAnalysis of the UPTF separate effects test 11 (steam-water countercurrent flow in the broken loop hot leg) using RELAP5/MOD2 /prepared by M.J. DillistoneWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,June 1992.1 online rsesource (vi, 24 pages) illustrationsInternational agreement report ;NUREG/IA-0071"AEEW-M2555.""Winfrith Technology Centre, United Kingdom Atomic Energy Authority.""June 1992.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP).""Type of report: technical"--Bibliographic data sheet.Includes bibliographical references (page 14).Analysis of the UPTF separate effects test 11 Pressurized water reactorsAccidentsData processingPressurized water reactorsTestingData processingPressurized water reactorsAccidentsData processing.Pressurized water reactorsTestingData processing.Dillistone M. J.1400998U.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910707782203321Analysis of the UPTF separate effects test 11 (steam-water countercurrent flow in the broken loop hot leg) using RELAP53468972UNINA