Experiment data report for Semiscale Mod-3 Lower Plenum Injection Test S-07-8 (baseline test series). [PWR]
Technical Report
·
OSTI ID:6110857
Recorded test data are presented for Test S-07-8 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-07-8 was conducted from initial conditions of 15.7 MPa and 556/sup 0/K to investigate the response of the Semiscale Mod-3 system to a blowdown transient following a simulated double-ended off-set 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.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6110857
- Report Number(s):
- NUREG/CR-0814; TREE-1228
- Country of Publication:
- United States
- Language:
- English
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21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
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210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ECCS
ENERGY TRANSFER
ENGINEERED SAFETY SYSTEMS
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FLUID FLOW
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LIQUID FLOW
LOSS OF COOLANT
MECHANICS
MOCKUP
PRESSURE GRADIENTS
PWR TYPE REACTORS
REACTOR ACCIDENTS
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REACTOR SAFETY
REACTORS
SAFETY
STRUCTURAL MODELS
TEST FACILITIES
WATER COOLED REACTORS
WATER MODERATED REACTORS