Experiment Data Report for Semiscale Mod-3 Blowdown Heat Transfer Test S-07-1 (Baseline Test Series)
USDOE, Benjamin Collins, USNRC, Kenneth Sackett, Kris Stanger
Abstract
USDOE, Benjamin Collins, USNRC, Kenneth Sackett, Kris Stanger
Abstract
Recorded test data are presented for Test S-07-1 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-07-1 was conducted from initial conditions of 15 878 kPa 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 establish the baseline performance of the Mod-3 system during a blowdown with cold leg emergency core coolant (ECC) injections. During the test, cooling water was injected into the cold leg of the intact and broken loops to simulate ECC injection in a PWR. The purpose of this report is to make available the uninterpreted data from Test S-07-1 for future data analysis and test reporting activities. 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-07-1 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-07-1 was conducted from initial conditions of 15 878 kPa 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 establish the baseline performance of the Mod-3 system during a blowdown with cold leg emergency core coolant (ECC) injections. During the test, cooling water was injected into the cold leg of the intact and broken loops to simulate ECC injection in a PWR. The purpose of this report is to make available the uninterpreted data from Test S-07-1 for future data analysis and test reporting activities. 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, Nuclear engineering, Thermal hydraulics, Pressurized water reactor, Coolant, Heat transfer, Environmental science