Transient thermal analysis of PWR’s by a single-pass procedure using a simplified nodal layout
Author(s)Liu, Jack S. H.; Todreas, Neil E.
PWR accident conditions and analysis methods have been reviewed. Limitations of the simplified method with respect to analysis of these accident conditions are drawn and two transients ( loss of coolant flow, seized rotor) identified as candidates for analysis by this method. These transients have been examined in detail by this one-stage approach (the simplified method). It is concluded that the steady state one-stage simplified method can be applied to the above two transient conditions.
Draft: June 1977, final: Feb. 1979.
MIT Energy Laboratory and Department of Nuclear Engineering
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