In-bundle void measurement of a BWR fuel assembly by an x-ray CT scanner: Assessment of BWR design void correlation and development of new void correlation

Akira Inoue*, Tatsuo Kurosu, Makoto Yagi, Shinichi Morooka, Akehiko Hoshide, Takao Ishizuka, Kunihiro Yoshimura

*この研究の対応する著者

研究成果: Conference contribution

16 被引用数 (Scopus)

抄録

Void fraction measurement tests for BWR fuel assemblies have been conducted as a Japanese national project mainly to prove the current BWR design void prediction method. The purpose of this study is to evaluate the BWR design void correlation and to develop the new void correlation. Void fraction was measured by the X-ray CT scanner. The tests have been carried out in an out-of-pile test facility that can simulate the high pressure and high temperature conditions of BWRs. An electrically heated test assembly simulates a BWR fuel assembly on a full scale. It was found that the void fractions predicted by the BWR design void correlation agree closely with the test measurements and the prediction accuracy was △̄α (average of difference between measure and calculation) = 2.1 % and σ (standard deviation of △̄α) = 3.0 %. In addition the new void correlation has been developed based on the drift flux model, and the prediction accuracy was △̄α = 0.3 % and σ = 1.9 %. The agreement with the published void data was fairly good.

本文言語English
ホスト出版物のタイトルProceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference
Place of PublicationNew York, NY, United States
出版社Publ by ASME
ページ39-45
ページ数7
出版ステータスPublished - 1993
外部発表はい
イベントProceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference. Part 1 (of 2) - San Francisco, CA, USA
継続期間: 1993 3 211993 3 24

Other

OtherProceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference. Part 1 (of 2)
CitySan Francisco, CA, USA
Period93/3/2193/3/24

ASJC Scopus subject areas

  • 工学(全般)

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