Experiment data report for Semiscale Mod-3 lower plenum injection test S-07-9 (baseline test series). [PWR]
Technical Report
·
OSTI ID:6394779
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.
- Research Organization:
- Idaho National Engineering Lab., Idaho Falls (USA)
- DOE Contract Number:
- EY-76-C-07-1570
- OSTI ID:
- 6394779
- Report Number(s):
- NUREG/CR-0815; TREE-1229
- Country of Publication:
- United States
- Language:
- English
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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
ENERGY TRANSFER
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MECHANICS
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REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
WATER COOLED REACTORS
WATER MODERATED REACTORS