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Author Faust, C. R. ♦ Hassan, Y. A.
Source United States Department of Energy Office of Scientific and Technical Information
Content type Text
Language English
Subject Keyword NUCLEAR REACTOR TECHNOLOGY ♦ NUCLEAR POWER REACTORS AND ASSOCIATED PLANTS ♦ BWR TYPE REACTORS ♦ LOSS OF COOLANT ♦ R CODES ♦ SIMULATION ♦ GE STANDARD REACTOR ♦ SAFETY ANALYSIS ♦ HYDRAULICS ♦ REACTOR SAFETY ♦ REACTOR COOLING SYSTEMS
Abstract The thermal-hydraulic simulation code RELAP5/MOD3. 1.1 was utilized to model General Electric`s simplified boiling water reactor plant. The model of the plant was subjected to a small-break loss-of-coolant accident (SBLOCA) occurring from a guillotine shear of the vessel`s 2-in. bottom drain line while operating at full power. The accident was compounded by disabling the plant`s isolation condenser system and, as an initial condition, the loss of site power. The ability of the plant`s passive safety system to respond to this type of accident and the code`s ability to accurately predict the accident`s phenomena were investigated.
ISSN 0003018X
Educational Use Research
Learning Resource Type Article
Publisher Date 1995-12-31
Publisher Place United States
Journal Transactions of the American Nuclear Society
Volume Number 73
Technical Publication No. CONF-951006-


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