Aerosol retention in HTGRs: A study on pool scrubbing of graphite and silica particles

IF 2.1 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2025-04-15 Epub Date: 2025-03-05 DOI:10.1016/j.nucengdes.2025.113972
Yating Wang , Zhikai You , Zhu Fang , Shumiao Zhao , Xinxin Wu , Libin Sun , Yiyang Zhang
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Abstract

The modular high-temperature gas-cooled reactor (HTGR) is recognized for the inherent safety, i.e., eliminating the possibility of core meltdown. Therefore, the source term becomes the main concern for HTGR accidents, with special focus on the graphite aerosol. However, there is few studies on the active control of graphite aerosol for HTGR. In this study, we propose a preliminary scheme for aerosol retention through pool scrubbing in HTGR water-ingress and loss-of-coolant accidents. The scrubbing characteristics of non-spherical graphite particles are investigated for different gas flow rates and submergences, and compared to the spherical silica particles. For both silica and graphite particles, the trend of decontamination factor (DF) is similar: slowly declining and then rapidly increasing with the increasing particle size. Further analysis with Stokes number indicates that the diffusion dominates below a critical Stokes number, while the inertia impact becomes the main mechanism when above this critical Stokes number. Especially, the DF of graphite particles is significantly lower than that of silica particles in the inertia-controlled regime, due to its irregular shape, porous structure, and hydrophobic nature. A bubble-breaking element is introduced to enhance the retention efficiency of graphite particles, by promoting gas–liquid mixing and more importantly, reducing bubble size in the rising zone. The result shows an average improvement of 135% in scrubbing efficiency, accompanied by a minimal 12.4% increase in pressure drop. This study demonstrates that by introducing an optimized scrubber to the current reactor design, the source term of graphite aerosol can be largely reduced for HTGR accidents with fairly low cost.
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htgr中的气溶胶滞留:石墨和二氧化硅颗粒池擦洗的研究
模块化高温气冷堆(HTGR)具有固有的安全性,即消除堆芯熔毁的可能性。因此,源项成为HTGR事故的主要关注点,特别是石墨气溶胶。然而,对高温气冷堆中石墨气溶胶的主动控制研究很少。在这项研究中,我们提出了一个初步方案,通过池擦洗在高温高温堆进水和冷却剂损失事故中气溶胶保留。研究了不同气体流速和浸没度下非球形石墨颗粒的洗涤特性,并与球形二氧化硅颗粒进行了比较。随着粒径的增大,二氧化硅和石墨颗粒的去污因子(DF)均呈现先缓慢下降后快速上升的趋势。利用Stokes数进一步分析表明,在某一临界Stokes数以下,扩散机制占主导地位,而在该临界Stokes数以上,惯性冲击机制成为主要机制。特别是在惯性控制下,石墨颗粒的DF明显低于二氧化硅颗粒,这是由于石墨颗粒的不规则形状、多孔结构和疏水性。为了提高石墨颗粒的保留效率,引入了破泡元件,通过促进气液混合,更重要的是减少上升区的气泡尺寸。结果表明,洗涤效率平均提高了135%,同时压降仅增加了12.4%。本研究表明,通过在现有反应堆设计中引入优化的洗涤器,可以以较低的成本大大降低HTGR事故中石墨气溶胶的源项。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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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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