Assessment of silicon carbide as a potential wall protection material for fusion reactors-Reference-Cited by-同舟云学术

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Assessment of silicon carbide as a potential wall protection material for fusion reactors

Published:1991-12 Issue: Volume:16 Page:311-316
ISSN:0920-3796
Container-title:Fusion Engineering and Design
language:en
Short-container-title:Fusion Engineering and Design

Author:

Dienst W.

Publisher

Elsevier BV

Subject

Mechanical Engineering,General Materials Science,Nuclear Energy and Engineering,Civil and Structural Engineering

Reference14 articles.

1. High heat flux experiments on ceramics: Material selection for neutron irradiation tests;Linke;J. Nucl. Mater.,1988

2. Thermal shock resistances of AIN and SiC for first wall applications;Shibui;Nucl. Engrg. Des.,1989

3. Investigations on ceramic materials for fusion technology;Dienst;J. Nucl. Mater.,1990

4. Reduction of the thermal conductivity of SiC by radiation damage;Rohde;J. Nucl. Mater.,1991

5. Flexural strength of proof-tested and neutron-irradiated silicon carbide;Price;J. Nucl. Mater.,1982

Cited by 23 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Radiation Effects in SiC and SiC–SiC;Comprehensive Nuclear Materials;2020

2. Silicon carbide and its composites for nuclear applications – Historical overview;Journal of Nuclear Materials;2019-12

3. Radiation Effects in SiC and SiC–SiC;Comprehensive Nuclear Materials;2012

4. Stability of SiC and its composites at high neutron fluence;Journal of Nuclear Materials;2011-10

5. Handbook of SiC properties for fuel performance modeling;Journal of Nuclear Materials;2007-09

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