Transient thermal analysis of PWR’s by a single-pass procedure using a simplified nodal layout
Name
MIT-EL-77-008-12141665.pdf
Size
3.32 MB
Format
Adobe PDF
Checksum (MD5)
ed89cd2816fb118adda77c3d8579abb5
Author(s)
Liu, Jack S. H.
Todreas, Neil E.
Date Issued
1979
Publisher
MIT Energy Laboratory and Department of Nuclear Engineering
Series/Report no.
MIT-EL
77-008
Abstract
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.
Description
Draft: June 1977, final: Feb. 1979.
Persistent DSpace Link
