Browsing Department of Nuclear Engineering by Subject "Boiling water reactors -- Safety measures"
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Analyzing the safety impact of containment inerting at Vermont Yankee
(Cambridge, Mass. : Massachusetts Institute of Technology, [Dept. of Nuclear Engineering, 1980], 1980)Post-accident hydrogen generation in BWR containments is analyzed as a function of engineered hydrogen control system, assumed either nitrogen inerting or air dilution. Fault tree analysis was applied to assess the failure ... -
Application of time dependent unavailability analysis to standby safety systems
(Cambridge, Mass. : Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 1982, 1982)