The critical issues of SiC materials for future nuclear systems

被引：163

作者：

Li, Mian ^{[1
,2
]}

Zhou, Xiaobing ^{[1
]}

Yang, Hui ^{[1
]}

Du, Shiyu ^{[1
]}

Huang, Qing ^{[1
]}

机构：

[1] Chinese Acad Sci, Ningbo Inst Ind Technol, Engn Lab Specialty Fibers & Nucl Energy Mat, Ningbo 315201, Zhejiang, Peoples R China

[2] Univ Chinese Acad Sci, 19A Yuquan Rd, Beijing 10049, Peoples R China

来源：

SCRIPTA MATERIALIA | 2018年 / 143卷

基金：

中国国家自然科学基金;

关键词：

Nuclear materials; Silicon carbide; Interlayer; Joining; Corrosion; SILICON-CARBIDE COMPOSITES; DOSE NEUTRON-IRRADIATION; SIC/SIC COMPOSITES; MECHANICAL-PROPERTIES; MATRIX COMPOSITES; TI3SIC2; FIBER; MICROSTRUCTURE; TEMPERATURE; CERAMICS;

D O I：

10.1016/j.scriptamat.2017.03.001

中图分类号：

TB3 [工程材料学];

学科分类号：

0805 ; 080502 ;

摘要：

SiC ceramic and SiC-based composites are promising structural materials for nuclear applications. This paper gives a viewpoint of the basic characterization and research-highlights of SiC-based composites with respect to applications in future nuclear systems. In particular, the following aspects are considered: 1) SiC fiber, 2) inter phase, 3) SiC matrix, and 4) SiC joining. Furthermore, remaining challenges and specific technical issues of SiC-based composites for nuclear applications are discussed, and some suggestions to overcome these are proposed. (C) 2017 Acta Materialia Inc. Published by Elsevier Ltd. All rights reserved.

引用

页码：149 / 153

页数：5

共 42 条

[1] Phase stability, swelling, microstructure and strength of Ti3SiC2-TiC ceramics after low dose neutron irradiation [J].