Opportunities and limitations for ion beams in radiation effects studies: Bridging critical gaps between charged particle and neutron irradiations

SJ Zinkle, LL Snead - Scripta Materialia, 2018 - Elsevier
Ion beams are indispensible for understanding radiation effects in materials, enabling
access to conditions challenging to perform with neutrons. However, ion irradiations can …

In-situ TEM investigation on the evolution of He bubbles and dislocation loops in Ni-based alloy irradiated by H2+ & He+ dual-beam ions

Z Zhu, W Ji, H Huang - Journal of Materials Science & Technology, 2023 - Elsevier
The synergistic evolution mechanisms of He bubbles and dislocation loops under 30 keV H
2+ & H e+ dual-beam ions irradiation at 650° C in the Ni-based alloy GH3535, which is the …

Effects of irradiation temperature and dose rate on the mechanical properties of self-ion implanted Fe and Fe–Cr alloys

CD Hardie, CA Williams, S Xu, SG Roberts - Journal of Nuclear Materials, 2013 - Elsevier
Pure Fe and model Fe–Cr alloys containing 5, 10 and 14% Cr were irradiated with Fe+ ions
at a maximum energy of 2MeV to the same dose of 0.6 dpa at temperatures of 300° C, 400° …

Analysis of position-dependent cavity parameters in irradiated metals to obtain insight on fundamental defect migration phenomena☆

YR Lin, A Bhattacharya, SJ Zinkle - Materials & Design, 2023 - Elsevier
Motion of point defects is a fundamental process that governs microstructure and properties
of materials. Here, we examine the near-surface and grain boundary cavity swelling depth …

A quantitative method to determine the region not influenced by injected interstitial and surface effects during void swelling in ion-irradiated metals

Y Li, A French, Z Hu, A Gabriel, LR Hawkins… - Journal of Nuclear …, 2023 - Elsevier
We propose and demonstrate a microstructurally-based experimental method to quantitively
determine the depth regions in self-ion-irradiated metals that are affected by the injected …

Cavity swelling in irradiated materials

A Bhattacharya, SJ Zinkle - 2020 - osti.gov
Cavity swelling, due to three-dimensional clustering of vacancies, is an undesirable isotropic
volume expansion of materials under irradiation. This phenomenon occurs above stage-III …

Radiation response of alloy T91 at damage levels up to 1000 peak dpa

JG Gigax, T Chen, H Kim, J Wang, LM Price… - Journal of Nuclear …, 2016 - Elsevier
Ferritic/martensitic alloys are required for advanced reactor components to survive 500–600
neutron-induced dpa. Ion-induced void swelling of ferritic/martensitic alloy T91 in the …

Microstructural analysis of an HT9 fuel assembly duct irradiated in FFTF to 155 dpa at 443 C

BH Sencer, JR Kennedy, JI Cole, SA Maloy… - Journal of Nuclear …, 2009 - Elsevier
The majority of data on the irradiation response of ferritic/martensitic steels has been derived
from simple free-standing specimens irradiated in experimental assemblies under well …

Microstructural examination of neutron, proton and self-ion irradiation damage in a model Fe9Cr alloy

JC Haley, S de Moraes Shubeita, P Wady… - Journal of Nuclear …, 2020 - Elsevier
Transmission electron microscopy (TEM) was used to compare the microstructural defects
produced in an Fe9Cr model alloy during exposure to neutrons, protons, or self-ions …

Spatial ordering of nano-dislocation loops in ion-irradiated materials

SL Dudarev, K Arakawa, X Yi, Z Yao, ML Jenkins… - Journal of Nuclear …, 2014 - Elsevier
Defect microstructures formed in ion-irradiated metals, for example iron or tungsten, often
exhibit patterns of spatially ordered nano-scale dislocation loops. We show that such …