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 …
Designing radiation resistance in materials for fusion energy
Proposed fusion and advanced (Generation IV) fission energy systems require high-
performance materials capable of satisfactory operation up to neutron damage levels …
performance materials capable of satisfactory operation up to neutron damage levels …
[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 …
Oxidation protection of tungsten alloys for nuclear fusion applications: A comprehensive review
T Fu, K Cui, Y Zhang, J Wang, F Shen, L Yu… - Journal of Alloys and …, 2021 - Elsevier
As the most noticeable plasma-oriented material (PFM), metal tungsten is widely used in
nuclear fusion reactors. However, its oxidation resistance is poor at high temperatures …
nuclear fusion reactors. However, its oxidation resistance is poor at high temperatures …
A full tungsten divertor for ITER: Physics issues and design status
RA Pitts, S Carpentier, F Escourbiac, T Hirai… - Journal of Nuclear …, 2013 - Elsevier
Budget restrictions have forced the ITER Organization to reconsider the baseline divertor
strategy, in which operations would begin with carbon (C) in the high heat flux regions …
strategy, in which operations would begin with carbon (C) in the high heat flux regions …
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 …
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 …
Basic physical processes and reduced models for plasma detachment
PC Stangeby - Plasma Physics and Controlled Fusion, 2018 - iopscience.iop.org
The divertor of a tokamak reactor will have to satisfy a number of critical constraints, the first
of which is that the divertor targets not fail due to excessive heating or sputter-erosion. This …
of which is that the divertor targets not fail due to excessive heating or sputter-erosion. This …