基于光热反射技术的耐事故核燃料导热性质研究

王宇舟; 张强; 马显锋; 朱斐; 廖京京

doi:10.13832/j.jnpe.2024.S1.0096

基于光热反射技术的耐事故核燃料导热性质研究

doi: 10.13832/j.jnpe.2024.S1.0096

王宇舟^1,,
张强¹,
马显锋^1, ,,
朱斐¹,
廖京京²

1.
中山大学中法核工程与技术学院，广东珠海，519082
2.
中国核动力研究设计院，成都，610213

基金项目: 国家自然科学基金资助项目（12305326，U2032143，12205392）；广东省基础与应用基础重大科技专项（2019B030302011）；广东省国际科技合作基地项目（2020A0505020005）；珠海市珠港澳科技合作项目（ZH2207-7301-210009-P-WC）；中山大学中央高校基本科研业务费专项资助（23qnpy76）

详细信息

作者简介:
王宇舟（1992—），男，副教授，现主要从事耐事故燃料性能分析方面的研究，E-mail: wangyzh253@mail.sysu.edu.cn

通讯作者:
马显锋，E-mail: maxf6@mail.sysu.edu.cn

中图分类号: TL352
计量
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- HTML全文浏览量: 56
- PDF下载量: 25
- 被引次数: 0
出版历程
- 收稿日期: 2023-12-28
- 修回日期: 2024-03-27
- 刊出日期: 2024-06-15

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

1.
Sino-French Institute of Nuclear Engineering and Technology, Sun Yat-Sen University, Zhuhai, Guangdong, 519082, China
2.
Nuclear Power Institute of China, Chengdu, 610213, China

摘要

摘要: 为改善新型耐事故核燃料的导热性能，提高导热性能测试方法的检测效率和测试精度，本文介绍了具有高空间分辨率和高测试频率的光热反射技术，阐述了此类技术的基本原理、实验装置和测试方法，重点介绍了针对核燃料研究所发展的空间域光热反射技术。以离子辐照样品和包覆核燃料涂层为例，介绍了空间域光热反射技术在原位测试领域的应用场景。针对离子辐照样品的不均匀损伤分布，开发了多层传热模型用于更准确地表征材料导热性质，采用该技术获得了UO₂燃料热导率随着离子注入剂量的定量衰减规律；准确表征了包覆核燃料微球各涂层在高温下的热输运性质，结合微结构研究揭示了缺陷相对于热解炭涂层热导率的影响。光热反射技术为探究辐照损伤和结构缺陷对于核燃料热量传输的作用机制提供了有力工具，为进一步改进燃料性能、开发高精度的燃料仿真模型提供了参考依据。
- 耐事故核燃料 /
- 导热性质 /
- 光热反射技术
Abstract: 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 in-situ 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.
- Accident tolerant fuels /
- Thermal conductivity /
- Laser-based thermoreflectance

HTML全文

图 1 SDTR测量系统和2.6 MeV 质子在UO₂中的辐照损伤示意图^[10,16]

Figure 1. Schematic Diagram of SDTR Measurement System and Irradiation Damage of 2.6 MeV Proton in UO₂

下载: 全尺寸图片幻灯片

图 2 采用SDTR技术测量质子和氦离子辐照后UO₂燃料的导热性能^[20]

Figure 2. Employing SDTR to Obtain Thermal Conductivity of UO₂ under Proton and Helium Ion Irradiation

下载: 全尺寸图片幻灯片

图 3 TRISO燃料颗粒各涂层热导率和热扩散系数随温度的变化^[24]

Figure 3. Changes of Thermal Conductivity and Thermal Diffusion Coefficient of Coatings on TRISO Fuel Particles with Temperature

下载: 全尺寸图片幻灯片

表 1 铀和氧点缺陷对于晶格和声子散射的影响^[21-22]

Table 1. Impact of Uranium and Oxygen Frenkel Pair on Lattice and Phonon Scattering

缺陷对弛豫体积/Å³ 声子散射参数/(10⁴ K⁻⁴·s⁻¹)

铀缺陷对 50 44.9

氧缺陷对 10 17.8

下载: 导出CSV

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