Pressure measurement test of single elbow simulating na cooled fast reactor cold-leg piping

Shinji Ebara, Yuta Aoya, Tsukasa Sato, Hidetoshi Hashizume, Kazuhisa Yuki, Kosuke Aizawa, Hidemasa Yamano

Research output: Chapter in Book/Report/Conference proceedingConference contribution

Abstract

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.

Original languageEnglish
Title of host publication18th International Conference on Nuclear Engineering, ICONE18
Pages705-713
Number of pages9
EditionPARTS A AND B
DOIs
Publication statusPublished - 2010
Event18th International Conference on Nuclear Engineering, ICONE18 - Xi'an, China
Duration: 2010 May 172010 May 21

Publication series

NameInternational Conference on Nuclear Engineering, Proceedings, ICONE
NumberPARTS A AND B
Volume4

Other

Other18th International Conference on Nuclear Engineering, ICONE18
CountryChina
CityXi'an
Period10/5/1710/5/21

ASJC Scopus subject areas

  • Nuclear Energy and Engineering

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