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First-principles study on the corrosion characteristics of surface defects for fusion reactor blanket structural steel in liquid lead-lithium environment

Jiayin Zhang, Shengnan He, Xin Ding, Wenyi Ding, Jing Wang, Wei Yang, Wei Lu, Delin Chu, Weihua Wang

2026.1.1Journal of Nuclear Materials

DOI: 10.1016/j.jnucmat.2025.156191

Abstract

Abstract is not available.

Citation format

ZHANG, Jiayin, et al. First-principles study on the corrosion characteristics of surface defects for fusion reactor blanket structural steel in liquid lead-lithium environment. Journal of Nuclear Materials, 2026.