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Drag characteristics of micron-sized tungsten dust in high-Mach rarefied flow during in-vessel LOCA of fusion reactor with Maxwell slip/DSMC hybrid modeling

Zhijie Qin, Shichao Zhang, Zhen Wang, Zhibin Chen, Jiangtao Jia, Taosheng Li2026年2月Nuclear FusionIF 3出版社

In a fusion reactor, an in-vessel loss of coolant accident (LOCA) involving the helium-cooled blanket will lead to the resuspension and migration of tritiated and micron-sized tungsten dust deposited at the bottom of the vacuum vessel under high-speed helium jets, significantly increasing the radiological release hazard. Drag force dominates particle transport dynamics, yet conventional computational fluid dynamics (CFD) fails to accurately characterize particle-fluid interactions in high-speed and rarefied flow fields. This study proposes a hybrid framework combining CFD with the Maxwell slip boundary and direct simulation Monte Carlo to simulate micron-particle drag force during in-vessel LOCA. The Cunningham drag correction formula accounting for wide-range Knudsen number (Kn) rarefied helium flow (0.01 < Kn < 2 × 104) was established using nonlinear least-squares fitting. Furthermore, by incorporating compressibility effects induced by high-Mach flow, a symbolic regression-based drag model was established as a function of Mach number (Ma) (0.033 < Ma < 1.31) and particle Reynolds number (1 × 10−4 < Rep < 50). This model provides critical engineering guidance for predicting radioactive dust migration in fusion reactors and the proposed framework could be extendable to loss of vacuum accidents and other engineering applications involving particle drag in high-Mach rarefied gas flows.

wiki

TungstenIn-vessel componentsLoss-of-coolant accident

AIによる論文要約

核融合炉の真空容器内LOCA時における高マッハ数希薄流中のミクロンサイズタングステンダストの抗力特性:Maxwell slip/DSMCハイブリッドモデリング
JA核融合炉の安全性評価や放射性ダスト管理に携わる研究者・エンジニア。特に、LOCA時のダスト移行リスク評価を必要とする方。#核融合炉 #LOCA #タングステンダスト #DSMC #抗力学
LLM向け: {"Title": "Drag characteristics of micron-sized tungsten dust in high-Mach raref…

核融合炉で冷却材喪失事故(LOCA)が発生すると、高速ヘリウムジェットにより真空容器底部のトリチウム含有タングステンダストが再浮遊・移動し、放射能放出リスクが増大します。粒子の移動を支配する抗力を正確に評価するため、従来のCFDでは不十分な高マッハ数・希薄流れに対し、Maxwell slip境界条件とDSMCを組み合わせたハイブリッド手法を提案。幅広いクヌッセン数(0.01~2×10⁴)とマッハ数(0.033~1.31)に対応する抗力モデルを構築し、放射性ダストの移行予測に役立つ工学的指針を提供します。この枠組みは真空破損事故など他の工学的応用にも拡張可能です。

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