Microstructural evolution of 3C-SiC exposed to simultaneous neutron irradiation and helium implantation-Reference-Cited by-同舟云学术

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Microstructural evolution of 3C-SiC exposed to simultaneous neutron irradiation and helium implantation

Published:2018-10 Issue: Volume:509 Page:366-376
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Hu Xunxiang,Koyanagi Takaaki,Zhao Jiangtao^ORCID,Yamamoto Takuya,Katoh Yutai^ORCID

Funder

US Department of Energy

Laboratory Directed R&D funds at ORNL

US Department of Energy Office of Fusion Energy Science

US-Japan TITAN project

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference42 articles.

1. Handbook of SiC properties for fuel performance modeling;Snead;J. Nucl. Mater.,2007

2. Properties of silicon carbide for nuclear fuel particle coatings;Price;Nucl. Technol.,1977

3. Motivation for utilizing new high-performance advanced materials in nuclear energy systems;Zinkle;Curr. Opin. Solid State Mater. Sci.,2016

4. Critical issues and current status of SiC/SiC composites for fusion;Hasegawa;J. Nucl. Mater.,2000

5. Status of silicon carbide composites for fusion;Snead;J. Nucl. Mater.,1996

Cited by 11 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. The synergetic effect of He and Kr irradiation on helium bubble evolution in SiC/SiC composite: Combining in-situ TEM observation with MD simulation;Journal of Materials Science & Technology;2024-10

2. Repelling effects of Mg on diffusion of He atoms towards surface in SiC: Irradiation and annealing experiments combined with first-principles calculations;Journal of Advanced Ceramics;2023-12

3. Evolution of microstructure and mechanical properties of SiCf/SiC composites induced by He ions irradiation at various temperatures;Ceramics International;2023-12

4. Microstructural evolution, swelling and hardening of CVD-SiC induced by He ions irradiation at 650 °C;Ceramics International;2023-01

5. Recovery and recrystallization of warm-rolled tungsten during helium thermal desorption spectroscopy annealing;Journal of Nuclear Materials;2022-10

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