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 …

A brief history of negative triangularity tokamak plasmas

A Marinoni, O Sauter, S Coda - Reviews of Modern Plasma Physics, 2021 - Springer
This review is devoted to tokamak plasmas with a cross sectional shape featuring negative
triangularity, which appear to hold great promise as a candidate reactor configuration owing …

[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 …

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 …

[图书][B] Magnetohydrodynamic stability of tokamaks

H Zohm - 2015 - books.google.com
This book bridges the gap between general plasma physics lectures and the real world
problems in MHD stability. In order to support the understanding of concepts and their …

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 …

Diverted negative triangularity plasmas on DIII-D: the benefit of high confinement without the liability of an edge pedestal

A Marinoni, ME Austin, AW Hyatt, S Saarelma… - Nuclear …, 2021 - iopscience.iop.org
Diverted discharges at negative triangularity on the DIII-D tokamak sustain normalized
confinement and pressure levels typical of standard H-mode scenarios (H 98y2≃ 1, β N≃ 3) …

New steady-state quiescent high-confinement plasma in an experimental advanced superconducting tokamak

JS Hu, Z Sun, HY Guo, JG Li, BN Wan, HQ Wang… - Physical review …, 2015 - APS
A critical challenge facing the basic long-pulse high-confinement operation scenario (H
mode) for ITER is to control a magnetohydrodynamic (MHD) instability, known as the edge …

[HTML][HTML] Development of a concept and basis for the DEMO diagnostic and control system

W Biel, M Ariola, I Bolshakova, KJ Brunner… - Fusion engineering and …, 2022 - Elsevier
An initial concept for the plasma diagnostic and control (D&C) system has been developed
as part of European studies towards the development of a demonstration tokamak fusion …