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Tungsten divertor erosion in all metal devices: Lessons from the ITER like wall of JET

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TLDR
Tungsten erosion in the outer divertor of the JET ITER like wall was quantified by spectroscopy as mentioned in this paper, and the signature of prompt redeposition was observed in the analysis of WI 400.
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This article is published in Journal of Nuclear Materials.The article was published on 2013-07-01 and is currently open access. It has received 113 citations till now. The article focuses on the topics: Divertor & Tungsten.

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Citations
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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.

Impact of nitrogen seeding on confinement and power load control of a high-triangularity JET

Abstract: This paper reports the impact on confinement and power load of the high-shape 2.5 MA ELMy H-mode scenario at JET of a change from all carbon plasma-facing components to an all metal wall. In preparation to this change, systematic studies of power load reduction and impact on confinement as a result of fuelling in combination with nitrogen seeding were carried out in JET-C and are compared with their counterpart in JET with a metallic wall. An unexpected and significant change is reported on the decrease in the pedestal confinement but is partially recovered with the injection of nitrogen.
Journal ArticleDOI

Residual carbon content in the initial ITER-Like Wall experiments at JET

TL;DR: The residual carbon content and carbon edge flux in JET have been assessed by three independent diagnostic techniques after start of plasma operation with the ITER-Like Wall (ILW) with beryllium fi....
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Overview of the JET results

Francesco Romanelli, +1104 more
- 27 Mar 2015 - 
TL;DR: In this paper, a detailed analysis of the plasma-facing components of the day-one tungsten divertor in ITER-like wall has been carried out, showing that the pattern of deposition within the divertor has changed significantly with respect to the JET carbon wall campaigns due to the absence of thermally activated chemical erosion of beryllium in contrast to carbon.
References
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Journal Article

Plasma Physics and Controlled Nuclear Fusion Research

TL;DR: In this paper, the first experiments in JET have been described, which show that this large tokamak behaves in a similar manner to smaller tokak, but with correspondingly improved plasma parameters.
Journal ArticleDOI

Tungsten as target material in fusion devices

TL;DR: In this article, the suitability of tungsten as a divertor target material under the conditions of a high density and low temperature divertor was investigated in ASDEX Upgrade.
Journal ArticleDOI

Plasma-wall interaction and plasma behaviour in the non-boronised all tungsten ASDEX Upgrade

TL;DR: ASDEX Upgrade has successfully started the second experimental campaign with a full tungsten coverage of the plasma facing components and without using a boronisation for machine conditioning as discussed by the authors.
Journal ArticleDOI

Spectroscopic determination of impurity influx from localized surfaces

TL;DR: In this paper, the flux of an impurity released from a surface can be derived from spectroscopic measurements along a line-of-sight directed at the surface, and the application of the theory to impurity influxes in the JET Tokamak is described.
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Frequently Asked Questions (15)
Q1. What are the contributions in "Tungsten divertor erosion in all metal devices: lessons from the iter like wall of jet" ?

In this paper, Romanelli et al. quantified the tungsten source in the outer divertor of JET in its ITER-like wall configuration, and concluded that the erosion is mainly caused by beryllium, which is also the dominant impurity in the plasma. 

Assuming that no atoms escape from the plasma before being ionized, the particle flux can be inferred from an absolutely measured atomic line intensity using the so-called S/XB method [1]. 

Starting from the highest temperatures, the tungsten sputtering increases steeply upon nitrogen seeding, evidently due to sputtering by nitrogen. 

Impurity seeding to reduce power and energy loads on divertor targets (e.g. [14, 15] and references therein) will add extrinsic impurities to the species mix. 

The nitrogen seeding starts to have a net beneficial effect, i.e. a reduction in the tungsten erosion, when the temperature drops below 15 eV.7 

The KS3 and PMT systems view 10 chords of 20 mm diameter using fiber optics, therewith also covering the horizontal target plate. 

A calculation of the promptly redeposited tungsten fraction predicts an order of magnitude lower net erosion,i.e. number of particle that really leave the target surface, compared to the gross erosion that has been characterized in the present work. 

For the present analysis, the authors have not applied the calculated S/XB values because the uncertainty in the tungsten ground state temperature introduces an uncertainty in the S/XB value of an order of magnitude. 

The top panel shows that this leads initially to a steep increase in the tungsten sputtering due to higher concentrations impurities (i.e. nitrogen), whereafter plasma cooling takes over to decrease the sputtering. 

The authors performed a consistency check on the integrated outer divertor particle flux (i.e. integrated over the strike point on the horizontal solid tungsten target plate) inferred from probe measurements and from Balmer epsilon intensity profiles. 

The error bar drawn in the figure for the effective erosion yields in JET reflects the two main uncertainties in the analysis: the value of the photon efficiency S/XB (including the underlying uncertainty in the plasma temperature) and the determination of the plasma flux. 

For the specific example, the inter-ELM sputtering amounted to 6.3 × 1018 atoms/s (following from integration over the entire outer strike point). 

The tungsten particle flux densities at the peak of the profile were normalized to the saturation current measured by Langmuir probes at the same radial position. 

For a magnetic field of 2.0 T, which was typical for the JET experiments discussed in the present paper, this resulted in the dependence plotted in Fig. 

These were determined before any boronization had been performed and were put in the perspective of sputtering by carbon impurities as a placeholder for all low-Z impurity ions present in the divertor target particle flux.