Abstract
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.
| Original language | English |
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| Title of host publication | Proceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference |
| Place of Publication | New York, NY, United States |
| Publisher | Publ by ASME |
| Pages | 39-45 |
| Number of pages | 7 |
| Publication status | Published - 1993 |
| Externally published | Yes |
| Event | Proceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference. Part 1 (of 2) - San Francisco, CA, USA Duration: 1993 Mar 21 → 1993 Mar 24 |
Other
| Other | Proceedings of the 2nd ASME-JSME Nuclear Engineering Joint Conference. Part 1 (of 2) |
|---|---|
| City | San Francisco, CA, USA |
| Period | 93/3/21 → 93/3/24 |
ASJC Scopus subject areas
- Engineering(all)