Silicon carbide and its composites for nuclear applications - Historical overview

被引:183
作者
Katoh, Yutai [1 ]
Snead, Lance L. [2 ,3 ]
机构
[1] Oak Ridge Natl Lab, 1 Bethel Valley Rd, Oak Ridge, TN 37831 USA
[2] SUNY Stony Brook, Stony Brook, NY 11794 USA
[3] MIT, Cambridge, MA 02139 USA
关键词
RESOLUTION ELECTRON-MICROSCOPY; CERAMIC-MATRIX COMPOSITES; ION IRRADIATION CREEP; NEUTRON-IRRADIATION; MECHANICAL-PROPERTIES; SIC/SIC COMPOSITES; SICF/SIC COMPOSITES; THERMAL-CONDUCTIVITY; ANNEALING BEHAVIOR; RADIATION-DAMAGE;
D O I
10.1016/j.jnucmat.2019.151849
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The goal of achieving higher thermal efficiency in nuclear power systems, whether fission or fusion based, has invariably led to the study and development of refractory metals, ceramics, and their composites. Silicon carbide materials, owing to their favorable neutronic and high-temperature properties, have seen extensive study for over half a century in support of this goal. Currently, our community has a relatively deep understanding of the irradiation effects on this system and has developed irradiation-hardened materials that are currently in use for fission reactor fuels and available as structural composites for next generation reactors. Outside of the nuclear arena SiC has also enjoyed significant development with a wide range of ordinary and high-value product now in use including very high temperature commercial aerospace installations such as turbine engines. The paper presents a brief history of the development of SiC, focused on but not limited to irradiation applications that has led to our present understanding of the system for nuclear application. (C) 2019 Elsevier B.V. All rights reserved.
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页数:24
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