Finite element analysis of droplet deposition in a BWR fuel subchannel around spacer using large Eddy simulation

Yasushi Yamamoto, Toru Mitsutake, Akihiko Hoshide, Shinichi Morooka

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

Abstract

In a boiling water nuclear reactor (BWR), liquid film dryout may occur on a fuel rod surface when the fuel assembly power exceeds the critical power. The spacers supporting fuel rods affect the thermal hydraulic performance of the fuel assembly. The spacer is designed to enhance the critical power significantly. If spacer effects for two-phase flow could be estimated analytically, the cost and time required for the development of the BWR fuel would be decreased. The final goal of this study is to be able to analytically predict the critical power of a new BWR fuel assembly without any tests. Initially, we focused on estimating the spacer effect on the droplet deposition because the spacer effect on the droplet deposition was larger than on the droplet entrainment. Therefore, the finite element method code with large eddy simulation model was developed to calculate the droplet behavior. Moreover, the estimation of droplet deposition around the two types of spacer was performed. The estimation results showed the tendency of deposited droplet volume to be in agreement with the tendency of the critical power.

Original languageEnglish
Title of host publicationAmerican Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED
Editors Anon
Place of PublicationNew York, NY, United States
PublisherASME
Volume16
Publication statusPublished - 1997
Externally publishedYes
EventProceedings of the 1997 ASME Fluids Engineering Division Summer Meeting, FEDSM'97. Part 16 (of 24) - Vancouver, Can
Duration: 1997 Jun 221997 Jun 26

Other

OtherProceedings of the 1997 ASME Fluids Engineering Division Summer Meeting, FEDSM'97. Part 16 (of 24)
CityVancouver, Can
Period97/6/2297/6/26

ASJC Scopus subject areas

  • Engineering(all)

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