Analysis of semiscale MOD-2A system UHI/SBLOCA experiments
Technical Report
·
OSTI ID:6162478
A series of six experiments was conducted in the Semiscale Mod-2A System, a scaled model of a pressurized water reactor (PWR), to investigate the influence of an upper head injection (UHI) emergency core cooling system on system response to small-break loss-of-coolant accidents (SBLOCAs). Three different cold leg break sizes were examined, simulating breaks of 2.5, 5, and 10% of the area of a PWR cold leg pipe. Thermal-hydraulic data on system response without UHI (baseline) and with UHI were obtained for each break area. The data were analyzed in terms of the influence of UHI and the influence of break size. Common SBLOCA signatures for various system parameters are identified. A convenient method of gauging the relative severity of each transient is presented.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA)
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6162478
- Report Number(s):
- NUREG/CR-3195; EGG-2246; ON: TI83011206
- Country of Publication:
- United States
- Language:
- English
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