Modeling of hydrogen isotope permeation through liquid Sn supported by various metal substrates

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Yuya Ando, Ryo Hatano, Ryosuke Ohata, Teppei Otsuka
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Abstract

Hydrogen isotope permeation through liquid Sn (SnL) supported by solid metals (M = Fe, Ni, V, F82H, and Pd) was examined at constant temperatures from 473 to 773 K and pressures from 0.67 to 93 kPa. The interaction between SnL and the supporting metal substrate formed an intermediate alloy (IA) layer at the interface due to corrosion caused by the chemical reactions of SnL with M. The SnL/M systems were categorized into two types according to the overall deuterium permeation behavior. In the SnL/Fe and SnL/Ni systems, the IA layer was crucial in governing the overall deuterium permeation flux. In the SnL/Pd system, deuterium permeation was strongly suppressed by the IA layers, whereas in the SnL/V and SnL/F82H systems, the rate-determining step for the overall deuterium permeation flux was the SnL layer. The SnL/V system exhibited the highest deuterium permeation flux, which was less affected by the formation of the IA layer. This result highlights the potential of V and its alloys as membrane windows for tritium extraction from SnL by permeation.
氢同位素通过不同金属基质支撑的液态锡的渗透模拟
在温度为473 ~ 773 K,压力为0.67 ~ 93 kPa的条件下,研究了固体金属(M = Fe、Ni、V、F82H和Pd)负载的液态Sn (SnL)中氢同位素的渗透。由于SnL与M的化学反应引起的腐蚀,SnL与支撑金属基体的相互作用在界面处形成中间合金(IA)层。根据总体的氘渗透行为将SnL/M体系分为两种类型。在SnL/Fe和SnL/Ni体系中,IA层是控制总体氘渗透通量的关键。在SnL/Pd体系中,IA层强烈抑制了氘的渗透,而在SnL/V和SnL/F82H体系中,SnL层是总氘渗透通量的速率决定步骤。SnL/V体系的氘渗透通量最高,受IA层形成的影响较小。这一结果突出了V及其合金作为渗透法从SnL中提取氚的膜窗的潜力。
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来源期刊
Fusion Engineering and Design
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.
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