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] Divertor of the European DEMO: Engineering and technologies for power exhaust

JH You, G Mazzone, E Visca, H Greuner… - Fusion Engineering and …, 2022 - Elsevier
In a power plant scale fusion reactor, a huge amount of thermal power produced by the
fusion reaction and external heating must be exhausted through the narrow area of the …

[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 …

[HTML][HTML] Use of tungsten material for the ITER divertor

T Hirai, S Panayotis, V Barabash, C Amzallag… - Nuclear Materials and …, 2016 - Elsevier
Since the ITER divertor design includes tungsten monoblocks in the vertical target where
heat loads are maximal, the design to protect leading edges as well as technology R&D for …

Disruptions in ITER and strategies for their control and mitigation

M Lehnen, K Aleynikova, PB Aleynikov… - Journal of Nuclear …, 2015 - Elsevier
The thermal and electromagnetic loads related to disruptions in ITER are substantial and
require careful design of tokamak components to ensure they reach the projected lifetime …

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 …

Presentation of the new SOLPS-ITER code package for tokamak plasma edge modelling

X Bonnin, W Dekeyser, R Pitts, D Coster… - Plasma and Fusion …, 2016 - jstage.jst.go.jp
Simulations of ITER divertor performance, geometry optimization and estimates of key
related parameters such as fuelling throughput have historically relied on the SOLPS …

Accuracy and transferability of Gaussian approximation potential models for tungsten

WJ Szlachta, AP Bartók, G Csányi - Physical Review B, 2014 - APS
We introduce interatomic potentials for tungsten in the bcc crystal phase and its defects
within the Gaussian approximation potential framework, fitted to a database of first-principles …