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Experiment data report for Semiscale Mod-3 Lower Plenum Injection Test S-07-8 (baseline test series). [PWR]

K.E. Sackett, R.L. Gillins, Doni Pack

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Abstract

Recorded test data are presented for Test S-07-9 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-07-9 was conducted from initial conditions of 16.10 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 vessel lower plenum of the Mod-3 system. The purpose of this report is to make available the uninterpreted data from Test S-07-9 for future data analysis. The data, presented in the form of graphics in engineering units, have been analyzed only to the extent necessary to ensure that they are reasonable and consistent.

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What this paper is about

Recorded test data are presented for Test S-07-9 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-07-9 was conducted from initial conditions of 16.10 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 vessel lower plenum of the Mod-3 system. The purpose of this report is to make available the uninterpreted data from Test S-07-9 for future data analysis. The data, presented in the form of graphics in engineering units, have been analyzed only to the extent necessary to ensure that they are reasonable and consistent.

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Available abstract

Recorded test data are presented for Test S-07-9 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-07-9 was conducted from initial conditions of 16.10 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 vessel lower plenum of the Mod-3 system. The purpose of this report is to make available the uninterpreted data from Test S-07-9 for future data analysis. The data, presented in the form of graphics in engineering units, have been analyzed only to the extent necessary to ensure that they are reasonable and consistent.

Key concepts: Boiler blowdown, Plenum space, Piping, Pressurized water reactor, Test data, Nuclear engineering, Boiling water reactor, Test (biology)

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Experiment data report for Semiscale Mod-3 Lower Plenum Injection Test S-07-8 (baseline test series). [PWR] — Research Paper | ScholarLens