Proceedings of the Korean Nuclear Society Conference (한국원자력학회:학술대회논문집)
- 1997.05a
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- Pages.335-341
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- 1997
The Generic Analysis Method for Core Flow Instability
- Jun, Byung-Soon (Korea Nuclear Fuel Co.) ;
- Park, Eung-Jun (Korea Nuclear Fuel Co.) ;
- Park, Jong-Ryool (Korea Nuclear Fuel Co.)
- Published : 1997.05.01
Abstract
The generic analysis method for core flow instability is suggested to confirm that the core flow instability would not occur on PWR conditions. For the confirmation, the stability criteria of each fuel type are provided. Instability investigations in various accident conditions prove that the locked rotor accident is the most limiting case to instability. Parametric Effects are surveyed and in good agreement with available studies. The effects of heat flux distribution become negligible as the subcooling number is decreased. The power margin to instability is calculated quantitatively in various accident conditions.
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