dc.citation.conferencePlace |
JA |
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dc.citation.conferencePlace |
Kyoto |
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dc.citation.title |
2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017 |
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dc.contributor.author |
Jeong, YS |
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dc.contributor.author |
Bang, In Cheol |
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dc.date.accessioned |
2023-12-19T19:08:24Z |
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dc.date.available |
2023-12-19T19:08:24Z |
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dc.date.created |
2019-03-21 |
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dc.date.issued |
2017-04-24 |
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dc.description.abstract |
To pursue sustainability and safety enhancement of nuclear energy, molten salt reactor is regarded as a promising candidate among various types of gen-IV reactors. Besides, pyroprocessing, which treats molten salt containing fission products, should consider safety related to decay heat from fuel material. For design of molten salt-related nuclear system, it is required to consider both thermal-hydraulic characteristics and neutronic behaviors for demonstration. However, fundamental heat transfer study of molten salt in operation condition is not easy to be experimentally studied due to its large scale, high temperature condition as well as difficulties of treating fuel material. From that reason, numerical study can have benefit to investigate behaviors of liquid-fueled molten salt in real condition. In this study, open source CFD package OpenFOAM was used to analyze liquid-fueled molten salt loop having internal heat source as a first step of research. Among various molten salts considered as a candidate of liquidfueled molten salt reactors, in this study, FLiBe was chosen as liquid salt. For simulating heat generation from fuel material within fluid flow, volumetric heat source was set for fluid domain and OpenFOAM solver was modified as fvOptions as customized. To investigate thermal-hydraulic behavior of molten salt, CFD model was developed and validated by comparing experimental results in terms of heat transfer and pressure drop. As preliminary stage, 2D cavity simulations were performed to validate the modeling capacity of modified solver of OpenFOAM by comparison with those of ANSYS-CFX. In addition, cases of external heat flux and internal heat source were compared to configure the effect of heat source setting in various operation condition. As a result, modified solver of OpenFOAM considering internal heat source have sufficient modeling capacity to simulate liquid-fueled molten salt systems including heat generation cases. |
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dc.identifier.bibliographicCitation |
2017 International Congress on Advances in Nuclear Power Plants: A New Paradigm in Nuclear Power Safety, ICAPP 2017 |
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dc.identifier.issn |
0000-0000 |
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dc.identifier.scopusid |
2-s2.0-85036454402 |
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dc.identifier.uri |
https://scholarworks.unist.ac.kr/handle/201301/35121 |
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dc.language |
영어 |
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dc.publisher |
International Congress on Advances in Nuclear Power Plants, ICAPP |
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dc.title |
Numerical study on heat transfer characteristics of liquid-fueled molten salt using OpenFOAM |
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dc.type |
Conference Paper |
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dc.date.conferenceDate |
2017-04-24 |
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