Analytical study on effects of BWR fuel spacer on droplet deposition

Y. Yamamoto*, A. Hoshide, T. Mitsutake, Shinichi Morooka

*この研究の対応する著者

研究成果: Article査読

17 被引用数 (Scopus)

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 on the thermal-hydraulic performance of the fuel assembly. The spacer is designed to enhance critical power significantly. If spacer effects for two-phase flow could be estimated analytically, the cost and time for the development of the advanced BWR fuel would be certainly 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 thermal-hydraulic tests. Initially, we developed the finite element code to estimate spacer effects on the droplet deposition. Then, using the developed code, the spacer effects were estimated for various spacer geometries in a plane channel and one subchannel of BWR fuel bundle. The estimated results of the spacer effects showed a possibility to analytically predict the critical power of a BWR fuel assembly.

本文言語English
ページ(範囲)119-129
ページ数11
ジャーナルNuclear Engineering and Design
175
1-2
出版ステータスPublished - 1997 11 1
外部発表はい

ASJC Scopus subject areas

  • エネルギー工学および電力技術
  • 原子力エネルギーおよび原子力工学
  • 土木構造工学
  • 機械工学
  • 安全性、リスク、信頼性、品質管理

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