Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor

  • Choi, Won Jun
  • Park, Jae Hyung
  • Lee, Juhyeong
  • Im, Jihun
  • Cho, Yunsik
  • ... Kim, Sung Joong
  • 외 1명
Citations

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초록

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.

키워드

Circulation performanceHelium bubblingIntensified drag forceNumerical calculationPassive molten salt fast reactorTwo-phase flow experimentLARGE-EDDY SIMULATIONVISCOSITYFLOWDENSITY
제목
Experimental and numerical assessment of helium bubble lift during natural circulation for passive molten salt fast reactor
저자
Choi, Won JunPark, Jae HyungLee, JuhyeongIm, JihunCho, YunsikKim, YongheeKim, Sung Joong
DOI
10.1016/j.net.2023.12.016
발행일
2024-03
유형
Article
저널명
Nuclear Engineering and Technology
56
3
페이지
1002 ~ 1012