Fuel rod bowing
Technical Report
·
OSTI ID:4032616
The purpose of this investigation was to quantify the extent of fuel rod bowing in Westinghouse pressurized water reactors and to assess the effects of fuel rod bowing on plant safety and reliability. An empirical bow correlation was developed based on data from irradiated assemblies. Analyses conducted with these conservative empirical predictions show that: (1) generically identified DNBR margins are adequate to offset DNBR reductions due to rod bow, (2) the present design practice of increasing the highest calculated core peaking factor is sufficient to account for all deviations, including the effects of rod bow, and (3) fretting and corrosion of bowed rods are negligible. These conclusions indicate that fuel rod bowing results in no impact on plant safety or reliability. (auth)
- Research Organization:
- Westinghouse Electric Corp., Pittsburgh, Pa. (USA)
- NSA Number:
- NSA-33-025267
- OSTI ID:
- 4032616
- Report Number(s):
- WCAP--8692
- Country of Publication:
- United States
- Language:
- English
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