Post-critical heat flux heat transfer: a survey of current correlations and their applicability

Post-critical heat flux (CHF) heat transfer is of interest to nuclear engineers because of the need to compute the consequences which immediately follow power in excess of the CHF and the need to be able to determine when adequate cooling has been re-established once CHF has been exceeded. The various regimes of post-CHF heat transfer pertaining to pool boiling and flow boiling are delineated. The correlations appropriate to each regime are indicated and an attempt is made to assess their utility. (author)