Semiscale Mod-2A Intermediate Break Test series: test-results comparison. [PWR]

Results are presented from an analysis of Semiscale Mod-2A Intermediate Break Tests S-IB-1, -2, and -3. The tests were 100% (percentage of cold leg pipe flow area), 50%, and 21.7%, respectively, communicative cold leg break loss-of-coolant experiments. They were intended to provide reference data for evaluation and assessment of reactor safety code capabilities to predict integral blowdown, refill/reflood experiments for intermediate break sizes, and, particularly, to provide data to extend the code into the reflood regime. Comparisons of Semiscale intermediate break test results with those from large and small break tests provided characterization of the phenomena observed during the intermediate break tests. An additional objective of Test S-IB-3 was to provide reference data for comparison of Semiscale test results with results from LOFT Test L5-1 and LOBI Test B-R1M.