한국원자력학회:학술대회논문집 (Proceedings of the Korean Nuclear Society Conference)
- 한국원자력학회 1996년도 춘계학술발표회논문집(2)
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- Pages.284-289
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- 1996
Effects of Turbulent Mixing and Void Drift Models on the Predictions of COBRA-IV-I
- Yoo, Yeon-Jong (Korea Atomic Energy Research Institute) ;
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Hwang, Dae-Hyun
(Korea Atomic Energy Research Institute) ;
- Nahm, Kee-Yil (Korea Atomic Energy Research Institute) ;
- Sohn, Dong-Seong (Korea Atomic Energy Research Institute)
- 발행 : 1996.05.01
초록
The predictions of the COBRA-IV-I code with the modified turbulent mixing and void drift models have been compared with the diabatic two-phase flow data on equilibrium quality. The turbulent mixing model based on an equal mass exchange of the existing COBRA-IV-I code has been modified to that based on an equal volume exchange between adjacent subchannels, and a void drift model has been newly incorporated in the code. To evaluate the performance of the equal volume exchange turbulent mixing model and the effects of the void drift model, the diabatic steam-water two-phase flow data obtained for the 9-rod bundle test under the typical operating conditions of the boiling water reactor(BWR) conducted by the General Electric (GE) were analyzed by the modified COBRA-IV-I code. The analysis indicates that the equal volume exchange turbulent mixing model with void drift predicts the observed two-phase flow data trends better than the equal mass exchange model, and to predict the correct data trends a more physically based void drift model need to be developed.
키워드