Experimental Data Report for Semiscale Mod-3 Blowdown Heat Transfer Test S-07-3 (Baseline Series)
- Idaho National Engineering Laboratory (INEL), Idaho Falls, ID (United States)
Recorded test data are presented for Test S-07-3 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-07-3 was conducted from initial conditions of 15.90 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 (a) to evaluate the effects of containment pressure on end-of-blowdown conditions and (b) to assess the effect of locating the pressurizer in the broken loop rather than the intact loop. During the test, cooling water was injected into the cold leg of the intact loop to simulate emergency core coolant 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:
- 6560234
- Report Number(s):
- TREE--1223; NUREG/CR-0356
- Country of Publication:
- United States
- Language:
- English
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