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 …

Progress on the application of ELM control schemes to ITER scenarios from the non-active phase to DT operation

A Loarte, G Huijsmans, S Futatani, LR Baylor… - Nuclear …, 2014 - iopscience.iop.org
Progress in the definition of the requirements for edge localized mode (ELM) control and the
application of ELM control methods both for high fusion performance DT operation and non …

Review of recent works in development and evaluation of high-Z plasma facing materials

N Yoshida - Journal of Nuclear Materials, 1999 - Elsevier
This paper reviews the recent activities and results in development and evaluation of new
high-Z materials focusing on tungsten and its alloys. VPS-W coating on graphite and CFC …

Power and particle control

A Loarte, B Lipschultz, AS Kukushkin… - Nuclear …, 2007 - iopscience.iop.org
Progress, since the ITER Physics Basis publication (ITER Physics Basis Editors et al 1999
Nucl. Fusion 39 2137–2664), in understanding the processes that will determine the …

Powder Metallurgy Processing of a WxTaTiVCr High-Entropy Alloy and Its Derivative Alloys for Fusion Material Applications

OA Waseem, HJ Ryu - Scientific reports, 2017 - nature.com
The WxTaTiVCr high-entropy alloy with 32at.% of tungsten (W) and its derivative alloys with
42 to 90at.% of W with in-situ TiC were prepared via the mixing of elemental W, Ta, Ti, V and …

Hydrogen in tungsten: Absorption, diffusion, vacancy trap**, and decohesion

DF Johnson, EA Carter - Journal of Materials Research, 2010 - cambridge.org
Understanding the interaction between atomic hydrogen and solid tungsten is important for
the development of fusion reactors in which proposed tungsten walls would be bombarded …

Metis: a fast integrated tokamak modelling tool for scenario design

JF Artaud, F Imbeaux, J Garcia, G Giruzzi, T Aniel… - Nuclear …, 2018 - iopscience.iop.org
METIS is a numerical code aiming at fast full tokamak plasma analyses and predictions. It
combines 0D scaling-law normalised heat and particle transport with 1D current diffusion …

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 …

Peripheral temperature gradient screening of high-Z impurities in optimised 'hybrid'scenario H-mode plasmas in JET-ILW

AR Field, FJ Casson, D Fajardo, C Angioni… - Nuclear …, 2022 - iopscience.iop.org
Screening of high-Z (W) impurities from the confined plasma by the temperature gradient at
the plasma periphery of fusion-grade H-mode plasmas has been demonstrated in the JET …

Tungsten as first wall material in fusion devices

M Kaufmann, R Neu - Fusion Engineering and Design, 2007 - Elsevier
The observation in JET of co-deposition of tritium with carbon has led to a broad discussion
on the replacement of graphite by a high-Z material for the first wall coverage. Moreover, due …