01959nam 2200445I 450 991070762800332120161013104335.0(CKB)5470000002466261(OCoLC)960640659(EXLCZ)99547000000246626120161013j199004 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierAssessment of RELAP5/MOD2 code using loss of offsite power transient data of KNU #1 plant /prepared by Bud-Dong Chung, Hho-Jung Kim, Young-Jin LeeWashington, DC :Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,April 1990.1 online resource (v, 89 pages) illustrationsInternational agreement report ;NUREG/IA-0030."Nuclear Safety Center, Korea Advanced Energy Research Institute.""Department of Nuclear Engineering, Seoul National University.""April 1990.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the International Thermal-Hydraulic Code Assessment and Application Program (ICAP).""Technical"--Bibliographic data sheet.Includes bibliographical references (page 34).Pressurized water reactorsSafety measuresComputer programsTransients (Dynamics)Computer programsPressurized water reactorsSafety measuresComputer programs.Transients (Dynamics)Computer programs.Chung B. D(Bub Dong),1401000Kim H. J(Hho Jung),Lee Young JinU.S. Nuclear Regulatory Commission.Office of Nuclear Regulatory Research,GPOGPOBOOK9910707628003321Assessment of RELAP53468987UNINA