Vibration characteristics of fuel assemblies subjected to a boiling water two-phase parallel flow (part 2)
Book
·
OSTI ID:271935
- Nuclear Power Engineering Co., Tokyo (Japan)
- Toshiba Corp., Kawasaki, Kanagawa (Japan)
- Tokyo Inst. of Tech. (Japan)
Nuclear fuel integrity and reliability are very important in the design and operation of a nuclear power plant. The flow-induced vibration characteristics of nuclear fuel are one of the basic concerns of fuel structural design. In evaluating the fuel rod vibration characteristics of a newly designed fuel bundle, it is useful to build up a database of flow-induced vibration characteristics for different lattice types and spacer designs. Actual design experimental studies were carried out to confirm the reliability of high-burnup 8 x 8 fuel in BWRs, with respect to flow-induced vibrations; they were subjected to boiling water two-phase parallel flow conditions matching those in an operating BWR. The pressure fluctuation inside of a simulated fuel channel and the rod vibration response were measured in this experiment. It was determined that the rod vibration had good correlation with pressure fluctuation inside of a fuel channel. Fuel rod vibration magnitude was computed in several flow conditions by a numerical vibration analysis using the pressure fluctuation as external force, and the computed results were in a good agreement with the tendency of measurement data. It was determined that the fuel rod vibration was caused by the pressure fluctuation excited in boiling water two-phase flow.
- OSTI ID:
- 271935
- Report Number(s):
- CONF-960306--; ISBN 0-7918-1226-X
- Country of Publication:
- United States
- Language:
- English
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