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 |
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ホスト出版物のタイトル | Proceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference |
Place of Publication | New 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月 21 → 1993 3月 24 |
Other
Other | Proceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference. Part 1 (of 2) |
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City | San Francisco, CA, USA |
Period | 93/3/21 → 93/3/24 |
ASJC Scopus subject areas
- 工学(全般)