B Duan, C Heintze, F Bergner, A Ulbricht… - Journal of Nuclear …, 2017 - Elsevier
Oxide dispersion strengthened (ODS) Fe-Cr alloys are promising candidates for structural components in nuclear energy production. The small grain size, high dislocation density and …
C Zhao, R Xie, C Xu, X Tian, Q Wang, W Jiang… - Acta Mechanica Solida …, 2024 - Springer
Single-phase concentrated solid solution alloys (SP-CSAs), including high-entropy alloys, have received extensive attention due to their excellent irradiation resistance. In this work …
The design of high irradiation-resistant materials is very important for the development of next-generation nuclear reactors. Grain boundaries acting as effective defect sinks are …
While the mechanically-induced martensitic transformation and transformation-induced plasticity (TRIP) effects have various known benefits, transformation of blocky martensite can …
In-core or cladding structural materials exposed to heavy ion irradiation often suffer serious irradiation-induced damages. Introducing defect sinks can effectively mitigate irradiation …
Defect sinks, such as grain boundaries and phase boundaries, have been widely accepted to improve the irradiation resistance of metallic materials. However, free surface, an ideal …
Metallic materials produce various structural defects in the radiation environment, resulting in serious degradation of material properties. An important way to improve the radiation …
Nanocrystalline materials have been proposed as superior radiation tolerant materials in comparison to coarse grain counterparts. However, there is still a limited understanding …