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

*この研究の対応する著者

研究成果: Conference contribution

抄録

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.

本文言語English
ホスト出版物のタイトルAmerican Society of Mechanical Engineers, Fluids Engineering Division (Publication) FED
編集者 Anon
Place of PublicationNew York, NY, United States
出版社ASME
16
出版ステータスPublished - 1997
外部発表はい
イベントProceedings of the 1997 ASME Fluids Engineering Division Summer Meeting, FEDSM'97. Part 16 (of 24) - Vancouver, Can
継続期間: 1997 6月 221997 6月 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

  • 工学(全般)

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