Physics basis for the first ITER tungsten divertor
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 …
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 …
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 …
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 …
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 …
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 …
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 …
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
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 …
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
Simulations of ITER divertor performance, geometry optimization and estimates of key
related parameters such as fuelling throughput have historically relied on the SOLPS …
related parameters such as fuelling throughput have historically relied on the SOLPS …
Accuracy and transferability of Gaussian approximation potential models for tungsten
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 …
within the Gaussian approximation potential framework, fitted to a database of first-principles …