用于测量高温熔盐的高通量落球粘度计

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Alexander Levy , Yifan Zhang , Haoxuan Yan , Anubhav Wadehra , Yu Zhong , Karl Ludwig , Uday Pal
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引用次数: 0

摘要

对清洁能源生产和储存的需求增加了人们对熔盐技术的兴趣,包括熔盐反应堆(MSR)。了解熔盐特性随温度和结构的变化对建立高效、经济的 MSR 系统至关重要。然而,对这些材料的研究一直受到限制,原因是很难在高温和受控环境下以省时高效的方式精确测量这些反应材料的特性。为解决这些问题,许多研究转向分子动力学(MD)建模。本研究介绍了一种定制的落球粘度计系统,用于快速测量熔盐粘度。此外,还开发了一个速度与 Re < 300 粘度相关的模型,供该系统使用。粘度计在共晶 FLiNaK 和 NaF-ZrF4 (53-47 mol%)上进行了演示,最高可达各自熔点以上 150 K。将结果与 MD 模拟进行了比较,以验证其预测粘度的有效性以及之前报告的测量结果。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
High-Throughput falling ball viscometer for measuring High-Temperature molten salts
The demand for clean energy production and storage has increased interest in molten salt technologies, including Molten Salt Reactors (MSR). Understanding of how molten salts properties change with respect to temperature and structure is vital to establishing efficient, cost effective MSR systems. Research into these materials however has been limited due to the difficulty in accurately measuring properties of these reactive materials at elevated temperatures and controlled environment in a time efficient way. Much research has turned to molecular dynamic (MD) modeling to alleviate these issues. This research presents a custom fabricated falling ball viscometer system for measuring molten salt viscosity quickly. A model for correlating velocity to viscosity for Re < 300 was also developed for use with this system. The viscometer is demonstrated on eutectic FLiNaK and NaF-ZrF4 (53–47 mol%) up to 150 K above the respective melting points. The results are compared to MD simulations to verify their effectiveness for predicting viscosity and previously reported measurements.
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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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