A Multi-Scale Simulation Study of Irradiation Swelling of Silicon Carbide

Silicon carbide (SiC) is a promising structural and cladding material for accident tolerant fuel cladding of nuclear reactor due to its excellent properties. However, when exposed to severe environments (e.g., during neutron irradiation), lattice defects are created in amounts significantly greater...

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Detalles Bibliográficos
Autores principales: Yin, Chunyu, Fu, Baoqin, Jiao, Yongjun, Duan, Zhengang, Wu, Lei, Zou, Yu, Liu, Shichao
Formato: Online Artículo Texto
Lenguaje:English
Publicado: MDPI 2022
Materias:
Article
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9102702/
https://www.ncbi.nlm.nih.gov/pubmed/35591343
http://dx.doi.org/10.3390/ma15093008

Internet

https://www.ncbi.nlm.nih.gov/pmc/articles/PMC9102702/
https://www.ncbi.nlm.nih.gov/pubmed/35591343
http://dx.doi.org/10.3390/ma15093008

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