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논문 기본 정보

자료유형
학술저널
저자정보
최원준 (한양대학교) 박재형 (한양대학교) 이주형 (한양대학교) 임지훈 (한양대학교) 조윤식 (한양대학교) 김용희 (한국과학기술원) 김성중 (한양대학교)
저널정보
한국원자력학회 Nuclear Engineering and Technology Nuclear Engineering and Technology Vol.56 No.3
발행연도
2024.3
수록면
1,002 - 1,012 (11page)
DOI
10.1016/j.net.2023.12.016

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To remove insoluble fission products, which could possibly cause reactor instability and significantly reduce heat transfer efficiency from primary system of molten salt reactor, a helium bubbling method is employed into a passive molten salt fast reactor. In this regard, two-phase flow behavior of molten salt and helium bubbles was investigated experimentally because the helium bubbles highly affect the circulation performance of working fluid owing to an additional drag force. As the helium flow rate is controlled, the change of key thermal-hydraulic parameters was analyzed through a two-phase experiment. Simultaneously, to assess the applicability of numerical model for the analysis of two-phase flow behavior, the numerical calculation was performed using the OpenFOAM 9.0 code. The accuracy of the numerical analysis code was evaluated by comparing it with the experimental data. Generally, numerical results showed a good agreement with the experiment. However, at the high helium injection rates, the prediction capability for void fraction of helium bubbles was relatively low. This study suggests that the multiphaseEulerFoam solver in OpenFOAM code is effective for predicting the helium bubbling but there exists a room for further improvement by incorporating the appropriate drag flux model and the population balance equation.

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