Nanocluster Evolution in D9 Austenitic Steel under Neutron and Proton Irradiation

Austenitic stainless steel D9 is a candidate for Generation IV nuclear reactor structural materials due to its enhanced irradiation tolerance and high-temperature creep strength compared to conventional 300-series stainless steels. But, like other austenitic steels, D9 is susceptible to irradiation-...

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Detalles Bibliográficos
Autores principales: Mullurkara, Suraj Venkateshwaran, Bejawada, Akshara, Sen, Amrita, Sun, Cheng, Bachhav, Mukesh, Wharry, Janelle P.
Formato: Online Artículo Texto
Lenguaje:English
Publicado: MDPI 2023
Materias:
Article
Acceso en línea:https://www.ncbi.nlm.nih.gov/pmc/articles/PMC10343310/
https://www.ncbi.nlm.nih.gov/pubmed/37445166
http://dx.doi.org/10.3390/ma16134852

Internet

https://www.ncbi.nlm.nih.gov/pmc/articles/PMC10343310/
https://www.ncbi.nlm.nih.gov/pubmed/37445166
http://dx.doi.org/10.3390/ma16134852

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