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无机材料学报

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核用SiC复合包壳多尺度力学损伤研究方法评述

黄淦1,2, 薛佳祥2, 檀财旺1, 刘洋2, 张国梁2, 杨正茂3, 陈招科4   

  1. 1.哈尔滨工业大学 材料结构精密焊接与连接全国重点实验室, 哈尔滨 150001;
    2.中广核研究院有限公司 核燃料与材料研究所, 深圳 518026;
    3.中国科学院力学研究所, 北京 100190;
    4.中南大学 粉末冶金国家重点实验室, 长沙 410083
  • 收稿日期:2025-12-14 修回日期:2026-02-09
  • 作者简介:黄淦(2003-), 男, 博士研究生. E-mail: 24B909009@stu.hit.edu.cn
  • 基金资助:
    国家自然科学基金(U24B2028)

Multiscale Methods for Investigating Mechanical Damage in Nuclear SiC Composite Cladding: A Review

HUANG Gan1,2, XUE Jiaxiang2, TAN Caiwang1, LIU Yang2, ZHANG Guoliang2, YANG Zhengmao3, CHEN Zhaoke4   

  1. 1. State Key Laboratory of Precision Welding & Joining of Materials and Structures, Harbin Institute of Technology, Harbin 150001, China;
    2. Nuclear Fuel and Materials Research Institute, China Nuclear Power Technology Research Institute, Shenzhen 518026, China;
    3. Institute of Mechanics, Chinese Academy of Sciences, Beijing 100190, China;
    4. State Key Laboratory of Powder Metallurgy, Central South University, Changsha 410083, China
  • Received:2025-12-14 Revised:2026-02-09
  • About author:HUANG Gan (2003-), male, PhD candidate. E-mail: 24B909009@stu.hit.edu.cn
  • Supported by:
    Natural National Science Foundation of China(U24B2028)

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摘要： SiC复合包壳因其高比强度、耐中子辐照和抗高温氧化等特性,有望替代传统锆合金包壳的颠覆性核燃料包壳技术。然而,SiC复合包壳的结构复杂,在服役条件下的力学失效行为尚不明确,制约了技术迭代与应用。为深入揭示SiC复合包壳损伤机理、预测极端环境下应力开裂风险并推进其工程应用,需开展系统性的多尺度力学损伤研究。本文围绕核用SiC复合包壳的多尺度力学损伤研究方法进行评述,涵盖宏观及微纳力学试验、基于数字图像相关、X射线计算机断层扫描和声发射等技术的原位监测与原位电镜表征,以及多尺度数值仿真等方面。目前该领域已取得重要进展：宏观力学测试可有效表征SiC复合包壳的整体力学性能,多种原位监测技术实现了包壳从表面到内部、从静态到动态的多维损伤演化观测,微纳力学测试为获取纤维、基体及界面等微区组元的力学参数提供了支撑,多尺度数值仿真则构建了从微观机制到宏观响应的有效关联与预测桥梁。最后,本文对该领域未来发展趋势与挑战进行了展望。

关键词: 核用SiC复合包壳, 多尺度力学测试, 原位表征, 多尺度数值仿真, 综述

Abstract: Silicon carbide (SiC) composite cladding has emerged as a disruptive fuel cladding technology in advanced nuclear energy systems, owing to its high specific strength, remarkable neutron irradiation resistance, and excellent high-temperature oxidation resistance, demonstrating significant potential to replace conventional zirconium alloy cladding. However, the structural complexity of SiC composites hinders a comprehensive understanding of their mechanical failure behavior under service conditions, which in turn constrains the pace of technological iteration. Therefore, to deeply reveal the damage mechanism of SiC composite cladding, accurately predict its stress-corrosion cracking risk in extreme environments, and further accelerate its engineering application, systematic multi-scale mechanical damage studies are essential. This review focuses on the research methodologies employed in multi-scale mechanical damage investigation of nuclear-grade SiC composite cladding. It covers macroscopic and micro‑/nano‑mechanical testing, in‑situ monitoring and characterization techniques such as digital image correlation, X‑ray computed tomography, and acoustic emission, as well as in‑situ electron microscopy characterization and multi‑scale numerical simulation. Significant progress has been achieved in this field: macroscopic mechanical tests can effectively characterize the overall mechanical performance of SiC composite cladding; multiple in‑situ techniques enable multi‑dimensional tracking of damage evolution from surface to interior and from static to dynamic processes; micro‑/nano‑mechanical testing provides critical support for obtaining mechanical parameters of key micro‑constituents, including fibers, matrix, and interfaces; and multi‑scale numerical simulations have established a predictive framework that effectively correlates microscopic mechanisms with macroscopic responses. Finally, prospects for future development and remaining challenges in this research area are outlined.

Key words: nuclear SiC composite cladding, multi-scale mechanical testing, in-situ characterization, multi-scale numerical simulation, review

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