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Journal ArticleDOI

Plasma operation with an all metal first-wall: Comparison of an ITER-like wall with a carbon wall in JET

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TLDR
In this paper, the ITER-like wall (ILW) was installed in the JET to enable a direct comparison of operation with all carbon plasma facing components (PFCs) to an all metal beryllium/tungsten first-wall under identical conditions.
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This article is published in Journal of Nuclear Materials.The article was published on 2013-07-01. It has received 146 citations till now. The article focuses on the topics: Tokamak.

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Fuel retention studies with the ITER-Like Wall in JET

TL;DR: In this article, the ITER-like wall (ILW) experiment at JET was used to demonstrate the plasma compatibility with metallic walls and the reduction in fuel retention, which confirmed the expected predictions concerning the plasma-facing material change in ITER and is in line with identification of fuel co-deposition with Be as the main mechanism for the residual long-term retention.
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Plasma-surface interaction in the Be/W environment: Conclusions drawn from the JET-ILW for ITER

TL;DR: The JET ITER-Like Wall experiment (JET-ILW) provides an ideal test bed to investigate plasma-surface interaction (PSI) and plasma operation with the ITER plasma-facing material selection employing beryllium in the main chamber and tungsten in the divertor.
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Overview of the JET results in support to ITER

X. Litaudon, +1228 more
- 15 Jun 2017 - 
TL;DR: In this paper, the authors reviewed the 2014-2016 JET results in the light of their significance for optimising the ITER research plan for the active and non-active operation, stressing the importance of the magnetic configurations and the recent measurements of fine-scale structures in the edge radial electric.
References
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Journal ArticleDOI

A full tungsten divertor for ITER: Physics issues and design status

TL;DR: In this article, the authors consider the risks engendered by the baseline divertor strategy with regard to known W plasma-material interaction issues and briefly present the current status of a possible full-tungsten (W) divertor design.
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Tungsten as material for plasma-facing components in fusion devices

TL;DR: In this paper, the use of tungsten (W) as material for plasma-facing components (PFM) in fusion devices is reviewed with respect to its plasma and material compatibility under burning plasmas conditions.
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Tritium inventory in ITER plasma-facing materials and tritium removal procedures

TL;DR: In this paper, the authors present an integrated operational scheme to slow the rate of tritium accumulation, which includes plasma operation as well as conditioning procedures, based on the main results from present fusion devices in this field.
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JET ITER-like wall - overview and experimental programme

TL;DR: In this article, the successful installation of the JET ITER-like wall and the realization of its technical objectives is reported, and an overview of the planned experimental program which has been optimized to exploit the new wall and other JET enhancements in 2011/12.
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Modelling of measured tungsten spectra from ASDEX Upgrade and predictions for ITER

TL;DR: In this paper, the spectral features of W at 0.4?0.8?nm, around 5?nm and around 12 and 14?nm have been recorded and compared with modelling results.
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