Methods for improving ductility of tungsten-a review

C Ren, ZZ Fang, M Koopman, B Butler… - International Journal of …, 2018 - Elsevier
Pure tungsten and tungsten alloys with minor alloying additions are known to be brittle at
room temperature and have high ductile-to-brittle transition temperatures (DBTT). Improving …

Recent progress in research on tungsten materials for nuclear fusion applications in Europe

M Rieth, SL Dudarev, SMG De Vicente, J Aktaa… - Journal of Nuclear …, 2013 - Elsevier
The current magnetic confinement nuclear fusion power reactor concepts going beyond
ITER are based on assumptions about the availability of materials with extreme mechanical …

Outstanding radiation resistance of tungsten-based high-entropy alloys

O El-Atwani, N Li, M Li, A Devaraj, JKS Baldwin… - Science …, 2019 - science.org
A body-centered cubic W-based refractory high entropy alloy with outstanding radiation
resistance has been developed. The alloy was grown as thin films showing a bimodal grain …

Interatomic potentials for modelling radiation defects and dislocations in tungsten

MC Marinica, L Ventelon, MR Gilbert… - Journal of Physics …, 2013 - iopscience.iop.org
We have developed empirical interatomic potentials for studying radiation defects and
dislocations in tungsten. The potentials use the embedded atom method formalism and are …

Hydrogen diffusion and vacancies formation in tungsten: density functional theory calculations and statistical models

N Fernandez, Y Ferro, D Kato - Acta Materialia, 2015 - Elsevier
The interaction of hydrogen with tungsten is investigated by means of the Density Functional
Theory (DFT) and statistical methods based on the transition-state theory and …

In-situ TEM studies of 150 keV W+ ion irradiated W and W-alloys: Damage production and microstructural evolution

X Yi, ML Jenkins, MA Kirk, Z Zhou, SG Roberts - Acta Materialia, 2016 - Elsevier
In-situ irradiations with 150 keV W+ ions have been performed on W and W-5wt.%(Re; Ta;
V) alloys in a comprehensive study of the influences of irradiation temperature T irr, dose …

A review of modelling and simulation of hydrogen behaviour in tungsten at different scales

GH Lu, HB Zhou, CS Becquart - Nuclear Fusion, 2014 - iopscience.iop.org
Tungsten (W) is considered to be one of the most promising plasma-facing materials (PFMs)
for next-step fusion energy systems. However, as a PFM, W will be subjected to extremely …

First-principles determination of grain boundary strengthening in tungsten: dependence on grain boundary structure and metallic radius of solute

X Wu, YW You, XS Kong, JL Chen, GN Luo, GH Lu… - Acta Materialia, 2016 - Elsevier
The control of segregation-induced grain boundary (GB) strengthening is a strategy for
improving the ductility and intergranular fracture of metals. In this work, by first-principles …

Characterisation of radiation damage in W and W-based alloys from 2 MeV self-ion near-bulk implantations

X Yi, ML Jenkins, K Hattar, PD Edmondson… - Acta Materialia, 2015 - Elsevier
The displacement damage induced in W and W-5 wt.% Re and W-5 wt.% Ta alloys by 2 MeV
W+ irradiation to doses 3.3× 10 17–2.5× 10 19 W+/m 2 at temperatures ranging from 300 to …

Short-range order in high entropy alloys: Theoretical formulation and application to Mo-Nb-Ta-VW system

A Fernández-Caballero, JS Wróbel… - Journal of Phase …, 2017 - Springer
In high-entropy alloys (HEAs), the local chemical fluctuations from disordered solute solution
state into segregation, precipitation and ordering configurations are complex due to the …