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 …
Results of high heat flux tests of tungsten divertor targets under plasma heat loads expected in ITER and tokamaks
VP Budaev - Physics of Atomic Nuclei, 2016 - Springer
Heat loads on the tungsten divertor targets in the ITER and the tokamak power reactors
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …
reach~ 10MW m− 2 in the steady state of DT discharges, increasing to~ 0.6–3.5 GW m− 2 …
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 …
Recent analysis of key plasma wall interactions issues for ITER
J Roth, E Tsitrone, A Loarte, T Loarer… - Journal of nuclear …, 2009 - Elsevier
Plasma wall interaction (PWI) is important for the material choice in ITER and for the plasma
scenarios compatible with material constraints. In this paper, different aspects of the PWI are …
scenarios compatible with material constraints. In this paper, different aspects of the PWI are …
Physics basis and design of the ITER plasma-facing components
RA Pitts, S Carpentier, F Escourbiac, T Hirai… - Journal of Nuclear …, 2011 - Elsevier
In ITER, as in any tokamak, the first wall and divertor plasma-facing components (PFC) must
provide adequate protection of in-vessel structures, sufficient heat exhaust capability and be …
provide adequate protection of in-vessel structures, sufficient heat exhaust capability and be …
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 …
Principal physics developments evaluated in the ITER design review
RJ Hawryluk, DJ Campbell, G Janeschitz… - Nuclear …, 2009 - iopscience.iop.org
As part of the ITER Design Review and in response to the issues identified by the Science
and Technology Advisory Committee, the ITER physics requirements were reviewed and as …
and Technology Advisory Committee, the ITER physics requirements were reviewed and as …
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 …
Performance of different tungsten grades under transient thermal loads
J Linke, T Loewenhoff, V Massaut, G Pintsuk… - Nuclear …, 2011 - iopscience.iop.org
Plasma facing components in future thermonuclear fusion devices will be subjected to
intense transient thermal loads due to type I edge localized modes (ELMs), plasma …
intense transient thermal loads due to type I edge localized modes (ELMs), plasma …
Effect of resonant magnetic perturbations on low collisionality discharges in MAST and a comparison with ASDEX Upgrade
Sustained edge localized mode (ELM) mitigation has been achieved on MAST and AUG
using resonant magnetic perturbations (RMPs) with various toroidal mode numbers over a …
using resonant magnetic perturbations (RMPs) with various toroidal mode numbers over a …