Experiment Data Report for Semiscale Mod-3 Blowdown Heat Transfer Test S-07-2 (Baseline Test Series)
- Idaho National Engineering Laboratory (INEL), Idaho Falls, ID (United States)
Recorded test data are presented for Test S-07-2 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-07-2 was conducted from initial conditions of 15.1 MPa and 558 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 objectives of this test were to assess the effect of radial power peaking on core thermal-hydraulic behavior and to evaluate the effect of emergency core coolant (ECC) subcooling on downcomer penetration characteristics in the Mod-3 system. During the test, cooling water was injected into the cold leg of the intact and broken loops to simulate ECC injection in a PWR.
- Research Organization:
- Idaho National Engineering Laboratory (INEL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE; USNRC
- DOE Contract Number:
- EY-76-C-07-1570;
- Other Award/Contract Number:
- NRC-FIN-A6038
- OSTI ID:
- 6763481
- Report Number(s):
- TREE--1222; NUREG/CR-0291
- Country of Publication:
- United States
- Language:
- English
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