气液接触器中氚输运的实现在ANSYS fluent中铅锂萃取氚的CFD模拟

IF 2 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY

Fusion Engineering and Design Pub Date : 2025-10-10 DOI:10.1016/j.fusengdes.2025.115479

Anthony G. Bowers Jr. , Subash L. Sharma , Thomas F. Fuerst

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引用次数: 0

摘要

对计算流体动力学（CFD）软件ANSYS Fluent进行了修改，以量化和表征氚在气液接触器（GLCs）中的输运。多孔介质模型采用双缝类厄根方程，并用Sulzer的Sulcol软件对厄根系数进行验证。用分析模型验证了GLC中氚从PbLi的输运。CFD模型的几何形状基于MELODIE GLC实验。流体动力学CFD压降结果与Sulcol的估计结果吻合良好，介于delft - olujiki和Billet及Schultes分析模型的预测结果之间。在传质效率方面，当使用不同的H溶解度值时，传统的传质模型与实验结果有很大的偏差。当氢在PbLi中使用高溶解度值时，会发生饱和现象。结合delft - olujiki或Billet和Schultes润湿性模型的改进膜理论传质系数得到了cfd预测的萃取效率，与实验测量结果非常吻合。

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Implementation of tritium transport in a gas-liquid contactor CFD simulation of tritium extraction from lead-lithium in ANSYS fluent

Modifications to the Computational Fluid Dynamic (CFD) software ANSYS Fluent were done to quantify and characterize tritium transport in gas-liquid contactors (GLCs). A double-slit, Ergun-like equation was employed for the porous media model, with Ergun coefficients validated with Sulzer’s Sulcol software. Tritium transport from PbLi within the GLC was verified against analytical models. The geometry of the CFD model was based on the MELODIE GLC experiment. The hydrodynamic CFD pressure drop results align well with Sulcol estimations and fall between the predictions of the analytical Delft-Olujić and Billet and Schultes models. In terms of mass transfer efficiency, traditional mass transfer models showed a significant deviation from experimental results when using varying values of H solubility in PbLi. A saturation phenomenon occurred when utilizing high solubility values for hydrogen in PbLi. A modified film theory mass transfer coefficient incorporating either the Delft-Olujić or Billet and Schultes wettability model yielded CFD-predicted extraction efficiencies that closely matched experimental measurements.

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来源期刊

Fusion Engineering and Design 工程技术-核科学技术

CiteScore

3.50

自引率

23.50%

发文量

275

审稿时长

3.8 months

期刊介绍： The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.