Remaining Uncertainties in Predicting the Coolability Limits of a Degraded Reactor Core (PWR; BWR)

摘要

The prediction of coolability limits of a degraded core is discussed with special emphasis on the areas of uncertainty. Where possible, the magnitude of the uncertainty is stated or estimated. The importance of using actual reactor debris properties in contrast to those of the spherical ball bearings or glass beads typically used in simulant experiments is stressed. Reviews of uncertainties in existing models and of potentially important, but as yet unexplained, anomalous experimental phenomena are also included. Finally, a listing of current research programs (USNRC, DOE and EPRI sponsored programs as well as foreign or independent programs in this and related areas) is provided with an assessment of probable contributions of these programs toward resolving remaining uncertainties. (ERA citation 08:049211)