Skip to main content
U.S. Department of Energy
Office of Scientific and Technical Information

Vibration characteristics of fuel assemblies subjected to a boiling water two-phase parallel flow (part 2)

Book ·
OSTI ID:271935
;  [1]; ; ;  [2];  [3]
  1. Nuclear Power Engineering Co., Tokyo (Japan)
  2. Toshiba Corp., Kawasaki, Kanagawa (Japan)
  3. 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

Similar Records

Space effect on liquid film flow in a BWR fuel bundle
Conference · Mon Dec 31 23:00:00 EST 1990 · Transactions of the American Nuclear Society; (United States) · OSTI ID:5779158

Large Eddy Simulation of turbulent flow in rod bundle with spacer grids
Journal Article · Sat Jul 01 00:00:00 EDT 2017 · Transactions of the American Nuclear Society · OSTI ID:23050419

Analysis of the effect of spacer shape on coolant flow in a nuclear fuel assembly
Conference · Tue Dec 31 23:00:00 EST 1991 · Transactions of the American Nuclear Society; (United States) · OSTI ID:7058225