1995•Unpublished venueOpen access
FIBWR2 evaluation of fuel thermal limits during density wave oscillaions in BWRs
Nuclear Regulatory Commission, Washington, DC (United States). Div. of Systems Technology, N. Nik, American Nuclear Society, La Grange Park, IL (United States), American Inst. of Chemical Engineers, New York, NY (United States), American Society of Mechanical Engineers, New York, NY (United States), Canadian Nuclear Society, Toronto, ON (Canada), Bern (Switzerland) European Nuclear Society (ENS), Tokyo (Japan) Atomic Energy Society of Japan, Kyoto (Japan) Japan Society of Multiphase Flow, S. Rajan, M. Karasulu
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Abstract
Analyses were performed to evaluate hydraulic and thermal margin responses of three different BWR fuel designs subjected to the same periodic power/flow oscillations, such as those that might be exhibited during an instability event. The power/flow versus time information from the oscillations was used as a forcing function to calculate the hydraulic response and the MCPR performance of the limiting fuel bundles during the regional oscillations using the analytical code FIBWR2. The results of the calculations were used to determine the thermal margin variation as a function of oscillation magnitude.