无机材料学报 ›› 2022, Vol. 37 ›› Issue (8): 821-840.DOI: 10.15541/jim20220145

• 综述 • 上一篇    下一篇

核用碳化硅纤维增强碳化硅复合材料研究进展

欧阳琴1,2(), 王艳菲1,2, 徐剑1,2, 李寅生1, 裴学良1,2, 莫高明1,2, 李勉1,2, 李朋1, 周小兵1,2, 葛芳芳1,2, 张崇宏2,3, 何流1,2, 杨磊2,3, 黄政仁1,2, 柴之芳1, 詹文龙2,3, 黄庆1,2()   

  1. 1.中国科学院 宁波材料技术与工程研究所, 宁波 315201
    2.先进能源科学与技术广东省实验室, 惠州 516000
    3.中国科学院 近代物理研究所, 兰州 730000
  • 收稿日期:2022-03-16 修回日期:2022-05-11 出版日期:2022-08-20 网络出版日期:2022-05-15
  • 通讯作者: 黄 庆, 研究员. E-mail: huangqing@nimte.ac.cn
  • 作者简介:欧阳琴(1981-), 男, 副研究员. E-mail: ouyangqin@nimte.ac.cn
  • 基金资助:
    宁波市“3315计划”A类创新团队和顶尖人才项目(2018A-03-A);先进能源科学与技术广东省实验室创新团队(HND20TDTHGC00);中国科学院战略性先导科技专项(A类)(XDA21010205)

Research Progress of SiC Fiber Reinforced SiC Composites for Nuclear Application

OUYANG Qin1,2(), WANG Yanfei1,2, XU Jian1,2, LI Yinsheng1, PEI Xueliang1,2, MO Gaoming1,2, LI Mian1,2, LI Peng1, ZHOU Xiaobing1,2, GE Fangfang1,2, ZHANG Chonghong2,3, HE Liu1,2, YANG Lei2,3, HUANG Zhengren1,2, CHAI Zhifang1, ZHAN Wenlong2,3, HUANG Qing1,2()   

  1. 1. Ningbo Institute of Materials Technology & Engineering, Chinese Academy of Sciences, Ningbo 315201, China
    2. Advanced Energy Science and Technology Guangdong Laboratory, Huizhou 516000, China
    3. Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
  • Received:2022-03-16 Revised:2022-05-11 Published:2022-08-20 Online:2022-05-15
  • Contact: HUANG Qing, professor. E-mail: huangqing@nimte.ac.cn
  • About author:OUYANG Qin (1981-), male, associate professor. E-mail: ouyangqin@nimte.ac.cn
  • Supported by:
    Ningbo “3315 Plan” Innovation Team Project and Top Talent Project(2018A-03-A);Advanced Energy Science and Technology Guangdong Laboratory(HND20TDTHGC00);CAS Priority Research program(XDA21010205)

摘要:

碳化硅纤维增强碳化硅(SiCf/SiC)复合材料具有低中子毒性、耐中子辐照和耐高温氧化等特性, 成为先进核能系统重要的候选结构材料。近年来, 国内外学术界和工业界针对核用SiCf/SiC复合材料开展了大量研究工作, 取得了一系列重要的研究进展。针对SiCf/SiC复合材料面向核用所关注的重点方向, 如核用SiC纤维、纤维/基体界面相、复合材料制备工艺、数值仿真、腐蚀行为和表面防护、连接技术以及辐照损伤等方面, 本文进行了综述和讨论, 并针对核用要求指出了SiCf/SiC复合材料存在的主要问题和可能的解决思路, 希望对该材料的进一步研发和最终应用有所裨益。

关键词: 复合材料, 结构材料, 核材料, 碳化硅, 辐照损伤, 综述

Abstract:

Silicon carbide fiber reinforced silicon carbide (SiCf/SiC) composites have become the preferred candidate for structural applications in advanced nuclear energy systems, because of their low neutron toxicity, neutron irradiation tolerance and high-temperature oxidation resistance. In recent years, both academia and industry either domestic or abroad have carried out a lot of researches on SiCf/SiC composites for nuclear application, and numerous important achievements have been made. This paper summarized and analysed some critical directions of SiCf/SiC composites for nuclear applications, including nuclear-grade SiC fibers, fibre/matrix interfaces, composite processing, modeling and simulation, corrosion behavior and surface protection, joining technology, as well as radiation damage. The key issues and potential solutions of SiCf/SiC composites for nuclear applications have been pointed out in account to the requirements, anticipating to be beneficial to promoting further researches and final applications.

Key words: composite material, structural material, nuclear material, silicon carbide, radiation damage, review

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