Evolution and characteristics of defect clusters in H2+ irradiated Al-based Gd2O3–W composites used as spent fuel shielding materials-Reference-Cited by-同舟云学术

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Evolution and characteristics of defect clusters in H2+ irradiated Al-based Gd2O3–W composites used as spent fuel shielding materials

Published:2023-06 Issue: Volume:34 Page:101295
ISSN:2468-6069
Container-title:Materials Today Energy
language:en
Short-container-title:Materials Today Energy

Author:

Wang Zuojiang,Cao Ziqi,Wu Mengjie,Li Yuanming,Ran Guang^ORCID

Publisher

Elsevier BV

Subject

Energy Engineering and Power Technology,Fuel Technology,Nuclear Energy and Engineering,Materials Science (miscellaneous),Renewable Energy, Sustainability and the Environment

Reference64 articles.

1. Status and Trends in Spent Fuel and Radioactive Waste Management,2018

2. Evolution of spent nuclear fuel in dry storage conditions for millennia and beyond;Wiss;J. Nucl. Mater.,2014

3. Materials challenges in nuclear energy;Zinkle;Acta Mater.,2013

4. Structural modifications of boron carbide irradiated by swift heavy ions;Pipon;J. Nucl. Mater.,2021

5. Effect of fast neutron irradiation on the structure of boron carbide;Hollenberg;J. Am. Ceram. Soc.,1977

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1. Effect of He/dpa ratio on bubble characteristics in Fe9Cr1.5W0.4Si F/M steel during irradiation and annealing;Journal of Materials Science & Technology;2024-10

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