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Experiment data report for Semiscale Mod-2A Intermediate Break Test Series (Tests S-IB-1 and S-IB-2). [PWR]
K.E. Sackett, L.B. Clegg
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Abstract
This report presents test data recorded for Tests S-IB-1 and S-IB-2 of the Semiscale Mod-2A Intermediate Break Test Series. These tests are part of a series of Semiscale tests that investigate the thermal-hydraulic phenomena resulting from a hypothesized loss-of-coolant accident (LOCA) in a pressurized water reactor (PWR) system. These tests provide experimental data for assessing the analytical capability of computer codes used in LOCA analysis. The primary objective of these tests is to expand the break data base to cover the 10% to 200% range. Tests S-IB-1 and S-IB-2 were communicative in nature and incorporated a 100% and 50% break orifice, respectively. Tests S-IB-1 and S-IB-2 were conducted from initial conditions closely approximating the specified initial conditions of: 15.5-MPa system pressure, 557-K cold leg temperature, and 1.95-MW core power level. This report presents uninterpreted data from both tests for future analysis.