Tritium inventory in ITER plasma-facing materials and tritium removal procedures

J Roth, E Tsitrone, T Loarer, V Philipps… - Plasma Physics and …, 2008 - iopscience.iop.org
Interactions between the plasma and the vessel walls constitute a major engineering
problem for next step fusion devices, such as ITER, determining the choice of the plasma …

Recent advances on hydrogen retention in ITER's plasma-facing materials: Beryllium, carbon, and tungsten

CH Skinner, AA Haasz, VK Alimov… - Fusion Science and …, 2008 - Taylor & Francis
Management of tritium inventory remains one of the grand challenges in the development of
fusion energy, and the choice of plasma-facing materials is a key factor for in-vessel tritium …

Fuel retention studies with the ITER-like wall in JET

S Brezinsek, T Loarer, V Philipps, HG Esser… - Nuclear …, 2013 - iopscience.iop.org
JET underwent a transformation from a full carbon-dominated tokamak to a fully metallic
device with beryllium in the main chamber and a tungsten divertor. This material …

High heat flux components—Readiness to proceed from near term fusion systems to power plants

AR Raffray, R Nygren, DG Whyte… - Fusion Engineering and …, 2010 - Elsevier
A present topic of high interest in magnetic fusion is the “gap” between near-term and long-
term concepts for high heat flux components (HHFC), and in particular for divertors. This …

Non-boronized compared with boronized operation of ASDEX Upgrade with full-tungsten plasma facing components

A Kallenbach, R Dux, M Mayer, R Neu… - Nuclear …, 2009 - iopscience.iop.org
After completion of the tungsten coating of all plasma facing components, ASDEX Upgrade
has been operated without boronization for 1 1/2 experimental campaigns. This has allowed …

Making tungsten work–ICFRM-14 session T26 paper 501 Nygren et al. making tungsten work

RE Nygren, R Raffray, D Whyte, MA Urickson… - Journal of Nuclear …, 2011 - Elsevier
Tungsten is the plasma-facing material of choice in several design studies for DEMOs and in
development programs for advanced plasma facing components. Use of tungsten in ITER for …

Ten years of W programme in ASDEX Upgrade—Challenges and conclusions

R Neu, V Bobkov, R Dux, JC Fuchs, O Gruber… - Physica …, 2009 - iopscience.iop.org
Since 1999 ASDEX Upgrade increased its tungsten plasma-facing components (PFCs) and
finally reached a full W coverage in 2007. Most of the initial goals of the investigations were …

Wall conditioning effects and boron migration during boron powder injection in ASDEX Upgrade

K Krieger, M Balden, A Bortolon, R Dux… - Nuclear Materials and …, 2023 - Elsevier
The efficacy of boron powder injection as a wall conditioning tool method in terms of its
ability to create a sufficiently uniform boron layer on plasma-facing surfaces has been …

Power load studies in JET and ASDEX-Upgrade with full-W divertors

B Sieglin, T Eich, A Scarabosio, G Arnoux… - Plasma Physics and …, 2013 - iopscience.iop.org
For the design and operation of large fusion devices, a detailed understanding of the power
exhaust processes is necessary. This paper will give an overview of the current research on …

Tungsten erosion and redeposition in the all-tungsten divertor of ASDEX Upgrade

M Mayer, M Andrzejczuk, R Dux… - Physica …, 2009 - iopscience.iop.org
Net erosion and deposition of tungsten (W) in the ASDEX Upgrade divertor were determined
after the 2007 campaign by using thin W marker stripes. ASDEX Upgrade had full-W plasma …