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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 …
JET ITER-like wall—overview and experimental programme
JET ITER-like wall—overview and experimental programme* Page 1 Physica Scripta JET
ITER-like wall—overview and experimental programme* To cite this article: GF Matthews et …
ITER-like wall—overview and experimental programme* To cite this article: GF Matthews et …
A full tungsten divertor for ITER: Physics issues and design status
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 …
Physics basis and design of the ITER plasma-facing components
In ITER, as in any tokamak, the first wall and divertor plasma-facing components (PFC) must
provide adequate protection of in-vessel structures, sufficient heat exhaust capability and be …
provide adequate protection of in-vessel structures, sufficient heat exhaust capability and be …
[HTML][HTML] Divertor plasma detachment
SI Krasheninnikov, AS Kukushkin, AA Pshenov - Physics of Plasmas, 2016 - pubs.aip.org
Regime with the plasma detached from the divertor targets (detached divertor regime) is a
natural continuation of the high recycling conditions to higher density and stronger impurity …
natural continuation of the high recycling conditions to higher density and stronger impurity …
Hydrogen diffusion and vacancies formation in tungsten: density functional theory calculations and statistical models
The interaction of hydrogen with tungsten is investigated by means of the Density Functional
Theory (DFT) and statistical methods based on the transition-state theory and …
Theory (DFT) and statistical methods based on the transition-state theory and …
Finalizing the ITER divertor design: The key role of SOLPS modeling
AS Kukushkin, HD Pacher, V Kotov, GW Pacher… - Fusion engineering and …, 2011 - Elsevier
The paper presents a review of the development of edge plasma modeling at ITER and of its
interaction with the evolving divertor design. The SOLPS (B2-Eirene) code has been …
interaction with the evolving divertor design. The SOLPS (B2-Eirene) code has been …
[HTML][HTML] Analytical expressions for thermophysical properties of solid and liquid tungsten relevant for fusion applications
The status of the literature is reviewed for several thermophysical properties of pure solid
and liquid tungsten which constitute input for the modelling of intense plasma-surface …
and liquid tungsten which constitute input for the modelling of intense plasma-surface …
ITER tungsten divertor design development and qualification program
T Hirai, F Escourbiac, S Carpentier-Chouchana… - Fusion Engineering and …, 2013 - Elsevier
Abstract In November 2011, the ITER Council has endorsed the recommendation that a
period of up to 2 years be set to develop a full-tungsten divertor design and accelerate …
period of up to 2 years be set to develop a full-tungsten divertor design and accelerate …
[HTML][HTML] Diagnostics for plasma control–From ITER to DEMO
The plasma diagnostic and control (D&C) system for a future tokamak demonstration fusion
reactor (DEMO) will have to provide reliable operation near technical and physics limits …
reactor (DEMO) will have to provide reliable operation near technical and physics limits …