HYDREX操作在聚变应用中从氦中除去氢的第一个实验结果

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Vincenzo Narcisi , Dario Diamanti , Daniele Martelli , Alessia Santucci
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引用次数: 0

摘要

从气态流出物中去除氚是未来核聚变发电厂部署的一个关键问题,当氚以百万分之一的数量级存在时更是如此。采用氧化层与沸石分子筛(Zeolite Molecular Sieve, ZMS)层相结合的方式净化氦冷却剂并覆盖气体,是一种很有前途的系统。在这项工作中,在氢气萃取(HYDREX)实验设施中研究了涉及这些技术的整体氦气净化过程,假设与EU-DEMO氦气冷却卵石床繁殖毯的冷却剂净化系统相关的边界条件。实验证明了高效的净化性能,可以去除96%的氢。然后,实验研究了一种合适的再生方法,使沸石材料的吸附性能得到了满意的恢复。一些开放的方面是个体化的,主要与通过ZMS床层的流动分布不均匀有关,导致床层较早饱和,沸石材料未完成再生。此外,由于未完成氧化,在再生的最初几分钟内会释放大量氢气。在这项工作中获得的结果是相关的进一步的实验研究的定义,并作为指导设计的气体除气系统。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
First experimental results of HYDREX operation in hydrogen removal from helium for fusion applications
The tritium removal from gaseous effluents represents a key issue for the deployment of future fusion power plants even more when tritium is present in the order of parts per million. A promising system derives from the fission experience, where oxidizing beds combined with Zeolite Molecular Sieve (ZMS) beds are adopted to purify helium coolant and cover gas. In this work, an integral helium purification process involving these technologies is studied in the Hydrogen Extraction (HYDREX) experimental facility assuming boundary conditions relevant for the Coolant Purification System of the EU-DEMO Helium Cooled Pebble Bed Breeding Blanket. The experimental campaign demonstrates the efficient purification performance allowing the removal of 96 % of the hydrogen. Then, a proper regeneration procedure is experimentally investigated providing a satisfactory restoring of the adsorption capability of the zeolite material. Some open aspects are individuated, mainly related to the uneven distribution of the flow through the ZMS bed causing an earlier saturation of the bed and a not completed regeneration of the zeolite material. Furthermore, a huge release of hydrogen in the first minutes of the regeneration is experienced due to the not completed oxidation. The results obtained in this work are relevant for the definition of further experimental investigations and as guidelines for the design of gas detritiation systems.
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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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