Protium enrichment by polymer electrolyte fuel cell with hydrogen gas circulation

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

Fusion Engineering and Design Pub Date : 2025-08-20 DOI:10.1016/j.fusengdes.2025.115399

Toranosuke Nago, Mikito Ueda, Hisayoshi Matsushima

引用次数: 0

Abstract

Hydrogen isotope separation is an important technology in various fields, including medicine, materials science, and nuclear energy. In this study, deuterium separation was performed using a polymer electrolyte fuel cell (PEFC) equipped with a gas circulation system. A hydrogen gas tank was integrated into the gas circulation line, enabling separation over a larger gas volume and achieving substantial H enrichment. The H concentration (C_H) in the hydrogen gas was monitored during the experiment using a mass spectrometer. During power generation, H was enriched in the hydrogen gas, and C_H increased from 24.2 at % to 54.6 at %. To evaluate the relationship between gas consumption and the H enrichment, the separation factor (αₜ) was considered. The value of α_t was higher than that of mass balance calculation. The present study suggested the separation was improved by the vapor phase chemical exchange reaction.

查看原文本刊更多论文

聚合物电解质燃料电池氢气循环富集Protium

氢同位素分离是医学、材料科学、核能等多个领域的重要技术。在这项研究中，使用配备气体循环系统的聚合物电解质燃料电池（PEFC）进行氘分离。一个氢气罐被集成到气体循环管线中，可以在更大的气体体积上进行分离，并实现大量的氢富集。在实验过程中，用质谱仪监测了氢气中的H浓度（CH）。发电过程中，H在氢气中富集，CH由24.2% at %增加到54.6% at %。为了评价气耗与H富集之间的关系，考虑了分离因子（α _l）。αt值大于质量平衡计算值。本研究表明，气相化学交换反应改善了分离效果。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

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.