First experimental results of HYDREX operation in hydrogen removal from helium for fusion applications

IF 1.9 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

Abstract

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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