Regarding the Japan Sodium-cooled Fast Reactor, a multi-elbow piping system is adopted for its cold-legs. Flow Induced Vibration (FIV) is considered to be caused by complex flow with very high velocity in the elbows. In this study, pressure measurement test of a single elbow flow is conducted to find out pressure fluctuation characteristic which is related to the elbow turbulent flow and lead potentially to the FIV. Two types of experimental loops, that is, 1/7 and 1/15-scale setup simulating the JSFR cold-leg pipings, are used for pressure measurement, and a distinguishing peak can be seen in the power spectrum density profile of pressure fluctuation obtained where flow separation occurs and at the downstream from it. This characteristics of pressure fluctuation is obtained from the two different scale experiments, and the scale effect is not found in terms of the pressure fluctuation.
- Nuclear Engineering Division
Pressure Measurement Test of Single Elbow Simulating Na Cooled Fast Reactor Cold-Leg Piping
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Ebara, S, Aoya, Y, Sato, T, Hashizume, H, Yuki, K, Aizawa, K, & Yamano, H. "Pressure Measurement Test of Single Elbow Simulating Na Cooled Fast Reactor Cold-Leg Piping." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 705-713. ASME. https://doi.org/10.1115/ICONE18-29719
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