[HTML][HTML] Perspectives on multiscale modelling and experiments to accelerate materials development for fusion

MR Gilbert, K Arakawa, Z Bergstrom, MJ Caturla… - Journal of Nuclear …, 2021 - Elsevier
Prediction of material performance in fusion reactor environments relies on computational
modelling, and will continue to do so until the first generation of fusion power plants come on …

Modeling microstructural evolution in irradiated materials with cluster dynamics methods: a review

AA Kohnert, BD Wirth, L Capolungo - Computational Materials Science, 2018 - Elsevier
As both the design of material systems for nuclear energy applications and the number of
reactor designs being proposed increase the need for material models predicting the …

Quantifying defect production in solids at finite temperatures: Thermally-activated correlated defect recombination corrections to DPA (CRC-DPA)

SJ Zinkle, RE Stoller - Journal of Nuclear Materials, 2023 - Elsevier
It has long been recognized from low-temperature defect production experiments and
molecular dynamics (MD) simulations of displacement events in metals that the surviving …

Stability and mobility of rhenium and osmium in tungsten: first principles study

T Suzudo, M Yamaguchi… - Modelling and Simulation …, 2014 - iopscience.iop.org
We report a series of ab initio studies based upon density functional theory for the behavior
of rhenium and osmium atoms in body-centered-cubic tungsten crystal. Contrary to the fast …

KineCluE: A kinetic cluster expansion code to compute transport coefficients beyond the dilute limit

T Schuler, L Messina, M Nastar - Computational Materials Science, 2020 - Elsevier
This paper introduces the KineCluE code that implements the self-consistent mean-field
theory for clusters of finite size. Transport coefficients are obtained as a sum over cluster …

[HTML][HTML] Multiscale modelling for fusion and fission materials: The M4F project

L Malerba, MJ Caturla, E Gaganidze, C Kaden… - Nuclear materials and …, 2021 - Elsevier
The M4F project brings together the fusion and fission materials communities working on the
prediction of radiation damage production and evolution and their effects on the mechanical …

Predicting displacement damage for ion irradiation: Origin of the overestimation of vacancy production in SRIM full-cascade calculations

YR Lin, SJ Zinkle, CJ Ortiz, JP Crocombette… - Current Opinion in Solid …, 2023 - Elsevier
Ion irradiation and implantation have wide applications that demand accurate determination
of displacement damage profile and distribution of implanted ion concentration. The …

A review of surface damage/microstructures and their effects on hydrogen/helium retention in tungsten

YG Li, QR Zheng, LM Wei, CG Zhang, Z Zeng - Tungsten, 2020 - Springer
The change in surface damage/microstructures and its effects on the hydrogen (H)
isotope/helium (He) dynamic behavior are the key factors for investigating issues of tungsten …

The co-evolution of microstructure features in self-ion irradiated HT9 at very high damage levels

E Getto, G Vancoevering, GS Was - Journal of Nuclear Materials, 2017 - Elsevier
Understanding the void swelling and phase evolution of reactor structural materials at very
high damage levels is essential to maintaining safety and longevity of components in Gen IV …

Migration of rhenium and osmium interstitials in tungsten

T Suzudo, M Yamaguchi, A Hasegawa - Journal of Nuclear Materials, 2015 - Elsevier
Tungsten is expected to be a promising plasma-facing material for future fusion devices, but
radiation-induced precipitation (RIP), which leads the material to hardening, is a concern at …