COBRA-WC pretest predictions and post-test analysis of the FOTA temperature distribution during FFTF natural-circulation transients
Description:
The natural circulation tests of the Fast Flux Test Facility (FFTF) demonstrated a safe and stable transition from forced convection to natural convection and showed that natural convection may adequately remove decay heat from the reactor core. The COBRA-WC computer code was developed by the Pacific Northwest laboratory (PNL) to account for buoyancy-induced coolant flow redistribution and interassembly heat transfer, effects that become important in mitigating temperature gradients and reducin…
more
Date:
June 23, 1982
Creator:
Khan, E. U.; George, T. L. & Rector, D. R.
Item Type:
Refine your search to only
Article
Partner:
UNT Libraries Government Documents Department