Physics basis for the first ITER tungsten divertor
On the eve of component procurement, this paper discusses the present physics basis for
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …
the first ITER tungsten (W) divertor, beginning with a reminder of the key elements defining …
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 …
Diamond Anniversary year. The present paper is part of a series in which single JNM …
[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 …
are diverse: the first wall will be exposed to extreme thermal loads of up to several tens of …
Edge-localized-modes in tokamaks
AW Leonard - Physics of Plasmas, 2014 - pubs.aip.org
Edge-localized-modes (ELMs) are a ubiquitous feature of H-mode in tokamaks. When
gradients in the H-mode transport barrier grow to exceed the MHD stability limit the ELM …
gradients in the H-mode transport barrier grow to exceed the MHD stability limit the ELM …
Research status and issues of tungsten plasma facing materials for ITER and beyond
Y Ueda, JW Coenen, G De Temmerman… - Fusion engineering and …, 2014 - Elsevier
This review summarizes surface morphology changes of tungsten caused by heat and
particle loadings from edge plasmas, and their effects on enhanced erosion and material …
particle loadings from edge plasmas, and their effects on enhanced erosion and material …
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 …
to high fluxes of low-energy particles (eg H, D, T, He, Ne and/or N). Combined with long …
Surface heat loads on the ITER divertor vertical targets
JP Gunn, S Carpentier-Chouchana, F Escourbiac… - Nuclear …, 2017 - iopscience.iop.org
The heating of tungsten monoblocks at the ITER divertor vertical targets is calculated using
the heat flux predicted by three-dimensional ion orbit modelling. The monoblocks are …
the heat flux predicted by three-dimensional ion orbit modelling. The monoblocks are …
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 …
and particle flux. Tungsten and Copper alloys are primary candidates for plasma facing …
Liquid metals as a divertor plasma-facing material explored using the Pilot-PSI and Magnum-PSI linear devices
TW Morgan, P Rindt, GG Van Eden… - Plasma Physics and …, 2017 - iopscience.iop.org
For DEMO and beyond, liquid metal plasma-facing components are considered due to their
resilience to erosion through flowed replacement, potential for cooling beyond conduction …
resilience to erosion through flowed replacement, potential for cooling beyond conduction …
Material testing facilities and programs for plasma-facing component testing
Component development for operation in a large-scale fusion device requires thorough
testing and qualification for the intended operational conditions. In particular environments …
testing and qualification for the intended operational conditions. In particular environments …