Experiment data report for semiscale Mod-3 integral blowdown and reflood heat transfer test S-07-6 (Baseline Test Series). [PWR]
V. Esparza, K.E. Sackett, K Stanger
Abstract
V. Esparza, K.E. Sackett, K Stanger
Abstract
Recorded test data are presented for Test S-07-6 of the Semiscale Mod-3 baseline test series. This test is one of several Semiscale Mod-3 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-07-6 was conducted from initial conditions of 15.21 MPa and 559 K to investigate the response of the Semiscale Mod-3 system to a blowdown transient following a simulated double-ended offset shear of the broken loop cold leg piping. The specific objective of this test was to provide reference data to evaluate integral blowdown and reflood behavior during a 200% cold leg break with emergency core coolant (ECC) injection into the intact loop cold leg of the Mod-3 system. The purpose of this report is to make available the uninterpreted data from Test S-07-6 for future data analysis. The data, presented in the form of graphs in engineering units, have been analyzed only to the extent necessary to ensure that they are reasonable and consistent.
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Recorded test data are presented for Test S-07-6 of the Semiscale Mod-3 baseline test series. This test is one of several Semiscale Mod-3 experiments conducted to investigate the thermal and hydraulic phenomena accompanying a hypothesized loss-of-coolant accident in a pressurized water reactor (PWR) system. Test S-07-6 was conducted from initial conditions of 15.21 MPa and 559 K to investigate the response of the Semiscale Mod-3 system to a blowdown transient following a simulated double-ended offset shear of the broken loop cold leg piping. The specific objective of this test was to provide reference data to evaluate integral blowdown and reflood behavior during a 200% cold leg break with emergency core coolant (ECC) injection into the intact loop cold leg of the Mod-3 system. The purpose of this report is to make available the uninterpreted data from Test S-07-6 for future data analysis. The data, presented in the form of graphs in engineering units, have been analyzed only to the extent necessary to ensure that they are reasonable and consistent.
Key concepts: Boiler blowdown, Piping, Test data, Nuclear engineering, Pressurized water reactor, Engineering, Environmental science, Mechanical engineering