A review on additive manufacturing of refractory tungsten and tungsten alloys

A Talignani, R Seede, A Whitt, S Zheng, J Ye… - Additive …, 2022 - Elsevier
We review the progress of additive manufacturing effort on refractory metal tungsten and
tungsten alloys. These materials are excellent candidates for a variety of high temperature …

Materials research for fusion

J Knaster, A Moeslang, T Muroga - Nature Physics, 2016 - nature.com
Fusion materials research started in the early 1970s following the observation of the
degradation of irradiated materials used in the first commercial fission reactors. The …

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 …

An integrated model for materials in a fusion power plant: transmutation, gas production, and helium embrittlement under neutron irradiation

MR Gilbert, SL Dudarev, S Zheng, LW Packer… - Nuclear …, 2012 - iopscience.iop.org
The high-energy, high-intensity neutron fluxes produced by the fusion plasma will have a
significant life-limiting impact on reactor components in both experimental and commercial …

Developing structural, high-heat flux and plasma facing materials for a near-term DEMO fusion power plant: The EU assessment

D Stork, P Agostini, JL Boutard, D Buckthorpe… - Journal of nuclear …, 2014 - Elsevier
The findings of the EU 'Materials Assessment Group'(MAG), within the 2012 EU Fusion
Roadmap exercise, are discussed. MAG analysed the technological readiness of structural …

In-situ TEM investigation of 30 keV he+ irradiated tungsten: Effects of temperature, fluence, and sample thickness on dislocation loop evolution

Y Li, L Wang, G Ran, Y Yuan, L Wu, X Liu, X Qiu, Z Sun… - Acta Materialia, 2021 - Elsevier
In-situ irradiations with 30 keV He+ were performed on tungsten in an investigation of the
influences of irradiation temperature and fluence, pre-existing dislocation and sample …

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 …

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 …

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 …