02038nam 2200469I 450 991070968900332120180521103713.0(CKB)5470000002471343(OCoLC)1036986293(EXLCZ)99547000000247134320180521j201611 ua 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierMain steam line break analysis for Lungmen ABWR /prepared by Chunkuan Shih [and five others]Washington, DC :Division of Systems Analysis, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission,November 2016.1 online resource (xiii, 24 pages) illustrationsInternational agreement report ;NUREG/IA-0476"Institute of Nuclear Engineering and Science, National Tsing Hua University; Nuclear and New Energy Education and Research Foundation.""Department of Nuclear Safety, Taiwan Power Company.""K. Tien, NRC project manager.""Manuscript completed: February 2016; date published: November 2016.""Prepared as part of the Agreement on Research Participation and Technical Exchange under the Thermal-Hydraulic Code Applications and Maintenance Program (CAMP)."Includes bibliographical references.Nuclear fuel rodsNuclear pressure vesselsBoiling water reactorsNuclear power plantsTaiwanSafety measuresNuclear fuel rods.Nuclear pressure vessels.Boiling water reactors.Nuclear power plantsSafety measures.Shih Chunkuan1389487U.S. Nuclear Regulatory Commission.Division of Systems Analysis,GPOGPOBOOK9910709689003321Main steam line break analysis for Lungmen ABWR3505661UNINA