Home / Publications / Journals / Nuclear Technology / Volume 83 / Number 3
Nuclear Technology / Volume 83 / Number 3 / December 1988 / Pages 252-273
Technical Paper / Fifth International Retran Meeting / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT88-A34140
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The Nuclear Safety Analysis Center (NSAC) at the Electric Power Research Institute has a Generic Safety Analysis Program to help resolve high-priority safety issues. Several high-priority safety issues considered at NSAC were resolved at least in part through the use of the RETRAN computer code. These issues are pressurized thermal shock, anticipated transients without scram in both pressurized and boiling water reactors, steam generator tube rupture, and scram frequency reduction.