对拟用于TER - RMSB的分子筛的高压水吸附性能进行了表征

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
George Ana, George Bulubasa, Alina Niculescu, Maria Craciun, Ciprian Bucur, Iuliana Stefan
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引用次数: 0

摘要

本研究调查了吹扫气体的总压和表面速度对 Na-Y 沸石吸附能力的影响,Na-Y 沸石是氦冷却卵石床(HCPB)氚提取和回收(TER)系统的候选材料。氚萃取和回收(TER)系统在预定的高压(8 兆帕)下从氦净化气体中捕获氚水蒸气,以减少与冷却气体之间的压差,提高系统的弹性。实验数据显示,虽然总压的增加会略微提高吸附能力,但较高的净化气体速度会降低吸附能力。使用 Langmuir、Sips 和 Freundlich 模型对吸附等温线进行了评估,其中 Sips 模型最接近实验数据。传质区(MTZ)分析表明,沿试验台的传质区形状稳定,这支持了研究结果在更大的 TER 系统中的可扩展性。在整个测试压力范围内,计算出的利用系数保持在 0.93-0.94 左右,但随着表层速度的增加而降低,这进一步为有效吸附的最佳操作参数和全尺寸设备的可扩展性提供了信息。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Characterization of water adsorption capacity at high pressure of the molecular sieve proposed to be used in TER RMSB
This study investigates the effects of total pressure and superficial velocity of purge gas on the adsorption capacity of Na-Y zeolite, a candidate material for the Tritium Extraction and Recovery (TER) system in the Helium Cooled Pebble Bed (HCPB) breeding blanket. The TER system captures tritiated water vapor from helium purge gas at intended high pressure (8 MPa) to reduce pressure differentials with the cooling gas and enhance system resilience. Experimental data reveal that, while total pressure increases marginally enhance adsorption capacity, higher purge gas velocities reduce it. Adsorption isotherms were evaluated using Langmuir, Sips, and Freundlich models, with the Sips model providing the closest fit to experimental data. Mass transfer zone (MTZ) analysis indicates a stable MTZ shape along the test bed, supporting scalability of the findings for larger TER systems. Calculated utilization factors remain around 0.93–0.94 across tested pressures but decrease with increasing superficial velocity, further informing optimal operational parameters for effective adsorption and scalability in full-scale equipment.
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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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