Physics basis for the first ITER tungsten divertor

RA Pitts, X Bonnin, F Escourbiac, H Frerichs… - Nuclear Materials and …, 2019 - Elsevier
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 …

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 …

[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 …

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 …

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 …

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 …

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 …

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 …

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 …

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 …