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

Authors
Choi, Won JunPark, Jae HyungLee, JuhyeongIm, JihunCho, YunsikKim, YongheeKim, Sung Joong
Issue Date
Mar-2024
Publisher
한국원자력학회
Keywords
Circulation performance; Helium bubbling; Intensified drag force; Numerical calculation; Passive molten salt fast reactor; Two-phase flow experiment
Citation
Nuclear Engineering and Technology, v.56, no.3, pp 1002 - 1012
Pages
11
Indexed
SCIE
SCOPUS
KCI
Journal Title
Nuclear Engineering and Technology
Volume
56
Number
3
Start Page
1002
End Page
1012
URI
https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/195464
DOI
10.1016/j.net.2023.12.016
ISSN
1738-5733
2234-358X
Abstract
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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COLLEGE OF ENGINEERING (DEPARTMENT OF NUCLEAR ENGINEERING)
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