Study on Thermal Conductivity of Accident Tolerant Fuels using Laser-based Thermoreflectance Technology

被引：0

作者：

Wang, Yuzhou ^{[1
]}

Zhang, Qiang ^{[1
]}

Ma, Xianfeng ^{[1
]}

Zhu, Fei ^{[1
]}

Liao, Jingjing ^{[2
]}

机构：

[1] Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Guangdong, Zhuhai

[2] Nuclear Power Institute of China, Chengdu

来源：

Hedongli Gongcheng/Nuclear Power Engineering | 2024年 / 45卷

关键词：

Accident tolerant fuels; Laser-based thermoreflectance; Thermal conductivity;

D O I：

10.13832/j.jnpe.2024.S1.0096

中图分类号：

学科分类号：

摘要：

In order to improve the thermal conductivity of new accident tolerant nuclear fuel and improve the detection efficiency and accuracy of thermal conductivity testing methods, this paper introduces the laser-based thermoreflectance technology with high spatial resolution and high testing frequency, expounds the basic principle, experimental equipment and testing method of this technology, and emphatically introduces the space-domain thermoreflectance technology developed for nuclear fuel research. Taking ion irradiated samples and coated nuclear fuel coatings as examples, the application scenarios of space-domain thermoreflectance technology in the field of insitu testing are introduced. Aiming at the inhomogeneous damage distribution of ion irradiated samples, a multi-layer heat transfer model was developed to characterize the thermal conductivity of materials more accurately, and the quantitative attenuation law of thermal conductivity of UO2 fuel with ion implantation dose was obtained by using this method. The heat transport properties of coatings in microencapsulated nuclear fuel particles at high temperature were accurately characterized, and the influence of defects on the thermal conductivity of pyrolytic carbon coatings was revealed by combining microstructure research. The thermoreflectance technology provides a powerful tool for investigating the impact of irradiation damage and structural defects on the thermal transport in nuclear fuel, and provides a reference for further improving fuel performance and developing high-fidelity simulation codes. © 2024 Atomic Energy Press. All rights reserved.

引用

页码：96 / 102

页数：6

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