A LARGE-SCALE PARTICLE-BASED SIMULATION OF HEAT AND MASS TRANSFER BEHAVIOR IN EAGLE ID1 IN-PILE TEST
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- Zhang Ting
- Kyushu University
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- Yao Yao
- Kyushu University
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- Morita Koji
- Kyushu University
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- Liu Xiaoxing
- Kyushu University
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- Liu Wei
- Kyushu University
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- Imaizumi Yuya
- Japan Atomic Energy Agency
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- Kamiyama Kenji
- Japan Atomic Energy Agency
説明
<p>The in-pile EAGLE ID1 test was conducted by Japan Atomic Energy Agency to demonstrate the effectiveness of the fuel assembly with an internal duct structure during a core disruptive accident in a sodium-cooled fast reactor. Post-test analysis using the SIMMER-III code are based on a multi-fluid model that uses empirical models in constitutive equations, making it difficult to accurately simulate multi-component, multi-phase flows with complex heat and mass transfer. In this study, a new computational fluid dynamics code based on the fully Lagrangian particle method was developed for the purpose of clarifying the failure mechanism of the inner duct wall of FAIDUS. The three-dimensional simulation of the ID1 test was performed to analyze a series of thermal hydraulic behaviors leading up to duct wall failure for a computational domain that included six fuel pins, i.e., 1/12.5 of the circumference of the test section. The simulations reasonably reproduced the heat transfer characteristics observed in the test, showing that the local contact of liquid steel with high thermal conductivity with the duct wall greatly enhances the heat transfer from the nuclear heating fuel to the duct wall. The present large-scale simulation produced the results that were essentially equivalent to those obtained in a smaller simulation system with three fuel pins in our previous work. The results support the validity of the conclusions of our analytical study regarding the molten pool-to-duct wall heat transfer mechanism that caused the thermal failure of the duct wall.</p>
収録刊行物
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- Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE
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Proceedings of the ... International Conference on Nuclear Engineering. Book of abstracts : ICONE 2023.30 (0), 1062-, 2023
一般社団法人 日本機械学会
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詳細情報 詳細情報について
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- CRID
- 1390579753343020672
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- ISSN
- 24242934
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- 本文言語コード
- en
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- データソース種別
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- JaLC
- Crossref
- OpenAIRE
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- 抄録ライセンスフラグ
- 使用不可