Behavior of tungsten under irradiation and plasma interaction

M Rieth, R Doerner, A Hasegawa, Y Ueda… - Journal of Nuclear …, 2019 - Elsevier
In 1959 the Journal of Nuclear Materials (JNM) was founded and is now celebrating its
Diamond Anniversary year. The present paper is part of a series in which single JNM …

Baseline high heat flux and plasma facing materials for fusion

Y Ueda, K Schmid, M Balden, JW Coenen… - Nuclear …, 2017 - iopscience.iop.org
In fusion reactors, surfaces of plasma facing components (PFCs) are exposed to high heat
and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing …

[HTML][HTML] Challenges for plasma-facing components in nuclear fusion

J Linke, J Du, T Loewenhoff, G Pintsuk… - Matter and Radiation …, 2019 - pubs.aip.org
The interaction processes between the burning plasma and the first wall in a fusion reactor
are diverse: the first wall will be exposed to extreme thermal loads of up to several tens of …

The influence of plasma-surface interaction on the performance of tungsten at the ITER divertor vertical targets

G De Temmerman, T Hirai, RA Pitts - Plasma Physics and …, 2018 - iopscience.iop.org
The tungsten (W) material in the high heat flux regions of the ITER divertor will be exposed
to high fluxes of low-energy particles (eg H, D, T, He, Ne and/or N). Combined with long …

Material testing facilities and programs for plasma-facing component testing

C Linsmeier, B Unterberg, JW Coenen… - Nuclear …, 2017 - iopscience.iop.org
Component development for operation in a large-scale fusion device requires thorough
testing and qualification for the intended operational conditions. In particular environments …

Overview of progress in European medium sized tokamaks towards an integrated plasma-edge/wall solution a

H Meyer, T Eich, M Beurskens, S Coda, A Hakola… - Nuclear …, 2017 - iopscience.iop.org
Integrating the plasma core performance with an edge and scrape-off layer (SOL) that leads
to tolerable heat and particle loads on the wall is a major challenge. The new European …

High-fluence and high-flux performance characteristics of the superconducting Magnum-PSI linear plasma facility

HJN Van Eck, GRA Akkermans… - Fusion Engineering and …, 2019 - Elsevier
The Magnum-PSI facility is unique in its ability to produce and even exceed the heat and
particle fluxes expected in the divertor of a fusion reactor, combined with good access to the …

Retarded recrystallization of helium-exposed tungsten

W Guo, L Cheng, G De Temmerman, Y Yuan… - Nuclear …, 2018 - iopscience.iop.org
In ITER and future tokamaks, recrystallization has been identified as an important issue
which may reduce the strength of tungsten plasma-facing component and deteriorate its …

DBTT and recrystallization behavior analyses for rolled and forged potassium-doped tungsten alloys

Y Tan, C Yu, J Wang, Y Lian, X Liu, F Feng, J Du… - Fusion Engineering and …, 2024 - Elsevier
Tungsten-potassium (WK) alloys are regarded as one of the candidates for plasma-facing
materials (PFMs) intended for the divertor and first wall of future fusion reactors. Determining …

Response of tungsten surfaces to helium and hydrogen plasma exposure under ITER relevant steady state and repetitive transient conditions

L Buzi, G De Temmerman, AE Huisman, S Bardin… - Nuclear …, 2017 - iopscience.iop.org
The effect of helium (He) plasma exposure, and associated surface modifications, on the
thermal shock resistance of tungsten (W) under ITER relevant steady state and transient …