Void swelling in additively manufactured 316L stainless steel with hafnium composition gradient under self-ion irradiation

M Song, J Yang, X Liu, LR Hawkins, Z Jiao, L He… - Journal of Nuclear …, 2023 - Elsevier
Compositionally-graded austenitic 316L stainless steel (SS) samples with five different
Hafnium (Hf) concentrations (up to 1 wt.%) were additively manufactured by directed energy …

The effect of the initial microstructure in terms of sink strength on the ion-irradiation-induced hardening of ODS alloys studied by nanoindentation

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 …

Molecular Dynamics Simulations of Displacement Cascade in Ni-Based Concentrated Solid Solution Alloys

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 …

Effect of grain boundary on the mechanical behaviors of irradiated metals: a review

XZ Xiao, HJ Chu, HL Duan - Science China Physics, Mechanics & …, 2016 - Springer
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 …

Composition-dependent transformation-induced plasticity in Co-based complex concentrated alloys

HS Oh, M Xu, S Wei, FF Worsnop, JM LeBeau… - Acta Materialia, 2024 - Elsevier
While the mechanically-induced martensitic transformation and transformation-induced
plasticity (TRIP) effects have various known benefits, transformation of blocky martensite can …

Microstructural changes and void swelling of a 12Cr ODS ferritic-martensitic alloy after high-dpa self-ion irradiation

T Chen, E Aydogan, JG Gigax, D Chen, J Wang… - Journal of Nuclear …, 2015 - Elsevier
A dual-phase 12Cr oxide-dispersion-strengthened (ODS) alloy, with improved corrosion and
oxidation resistance exhibits promising void swelling resistance and microstructural stability …

Response of solidification cellular structures in additively manufactured 316 stainless steel to heavy ion irradiation: an in situ study

Z Shang, C Fan, S Xue, J Ding, J Li… - Materials Research …, 2019 - Taylor & Francis
In-core or cladding structural materials exposed to heavy ion irradiation often suffer serious
irradiation-induced damages. Introducing defect sinks can effectively mitigate irradiation …

In situ study of defect migration kinetics in nanoporous Ag with enhanced radiation tolerance

C Sun, D Bufford, Y Chen, MA Kirk, YQ Wang, M Li… - Scientific reports, 2014 - nature.com
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 …

Understanding the Radiation Resistance Mechanisms of Nanocrystalline Metals from Atomistic Simulation

L Zhang - Metals, 2021 - mdpi.com
Metallic materials produce various structural defects in the radiation environment, resulting
in serious degradation of material properties. An important way to improve the radiation …

[HTML][HTML] Examining the influence of grain size on radiation tolerance in the nanocrystalline regime

CM Barr, N Li, BL Boyce, K Hattar - Applied Physics Letters, 2018 - pubs.aip.org
Nanocrystalline materials have been proposed as superior radiation tolerant materials in
comparison to coarse grain counterparts. However, there is still a limited understanding …