高温高温堆模拟工况下直管内石墨粉尘沉积实验研究

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Shulong Huang , Ziqi Jiang , Lixiao Guo , Jie Kong , Qiyuan Guan , Jialu Li , Yuhang Zhang , Ying Liu , Zhijie Gu
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引用次数: 0

摘要

高温气冷堆(HTGR),特别是像中国的HTR-PM这样的球床设计,提供了关键的安全和效率优势。然而,在长期运行过程中产生的放射性石墨粉尘给安全和维护带来了挑战。本研究通过实验研究了石墨粉尘在不同流速、温度和载气(空气和氦气)条件下在直管中的沉积和再悬浮。在上游、中游和下游位置测量沉积。结果表明,增加流速可显著减少沉积,与1.5 m/s相比,6 m/s流速可减少97.6%,9 m/s流速几乎可以消除沉积。轴向沉降保持一致,大部分粉尘沉降在前部和中部。较高的温度(25-300°C)可减少沉积并改善均匀性。氦气,由于其较高的粘度和较低的密度,导致较低的总体沉积比空气。再悬浮测试显示,在高风速(高达28米/秒)下,颗粒部分脱落,但无法完全再悬浮,这可能是由于静电相互作用等强附着力造成的。这些结果为CFD模型验证提供了关键的实验数据,并为制定有效的粉尘控制策略提供了支持,有助于HTGR更安全、更高效地运行。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Experimental study on graphite dust deposition in straight pipes under simulated HTGR operating conditions
The high-temperature gas-cooled reactor (HTGR), especially in the pebble-bed design like China’s HTR-PM, offers key safety and efficiency benefits. However, radioactive graphite dust generated during long-term operation poses safety and maintenance challenges. This study experimentally investigates graphite dust deposition and resuspension in a straight pipeline under varying flow velocities, temperatures, and carrier gases (air and helium). Deposition was measured at upstream, midstream, and downstream locations. Results show that increasing flow velocity significantly reduces deposition, with a 97.6 % decrease at 6 m/s compared to 1.5 m/s and near elimination at 9 m/s. Axial deposition remained consistent, with most dust settling in the front and middle sections. Higher temperatures (25–300 °C) reduced deposition and improved uniformity. Helium, due to its higher viscosity and lower density, led to lower overall deposition than air. Resuspension tests revealed partial particle detachment at high wind speeds (up to 28  m/s), but complete resuspension was not achieved, likely due to strong adhesion forces such as electrostatic interactions. These results provide critical experimental data for CFD model validation and support the development of effective dust control strategies, contributing to safer and more efficient HTGR operation.
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来源期刊
Nuclear Engineering and Design
Nuclear Engineering and Design 工程技术-核科学技术
CiteScore
3.40
自引率
11.80%
发文量
377
审稿时长
5 months
期刊介绍: Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.
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