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Global erosion and deposition patterns in JET with the ITER-like Wall

TLDR
A set of Be and W tiles removed after the first ITER-like wall campaigns (JET-ILW) from 2011 to 2012 has been analyzed in this article, and the results indicate that the primary erosion site is in the main chamber (Be) as in previous carbon campaigns.
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This article is published in Journal of Nuclear Materials.The article was published on 2015-08-01 and is currently open access. It has received 50 citations till now. The article focuses on the topics: Divertor.

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Deposition in the tungsten divertor during the 2011-2016 campaigns in JET with ITER-like wall

TL;DR: In this article, a build-up of co-deposits in remote areas of the divertor can contribute significantly to the overall fuel retention and control of plasma-material interactions via the study and understanding of...
Journal ArticleDOI

Be ITER-like wall at the JET tokamak under plasma

TL;DR: The JET tokamak is operated with beryllium and tungsten plasma-facing components to prepare for the exploitation of ITER, and a set of markers were used in this paper to determine the erosion and migration in JET.
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Demonstration of suppression of dust generation and partial reduction of the hydrogen retention by tungsten coated graphite divertor tiles in LHD

TL;DR: In this article, three sets of tungsten coated graphite divertor tiles (VPS-W tiles) were installed in the closed helical divertor of the Large Helical Device (LHD) instead of the graphite tiles in the 2012FY plasma campaign for examining the plasma wall interaction (PWI) with divertor plasma.
Journal ArticleDOI

Comparison of JET inner wall erosion in the first three ITER-like wall campaigns

TL;DR: The first three ITER-like wall (JET-ILW) campaigns were studied using long-term samples with Be and W marker layers, and the results showed that the erosion was roughly homogeneously distributed in both toroidal and poloidal directions with a small maximum near the middle of the inner wall and a minimum near the bottom of the wall, as well as several toroidal distribution features as mentioned in this paper.
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Journal ArticleDOI

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.
Journal ArticleDOI

Advanced physics and algorithms in the IBA DataFurnace

TL;DR: The IBA DataFurnace (NDF) as mentioned in this paper is a general purpose program for analysis of IBA data, which includes Rutherford backscattering, elastic (non-Rutherford) backscatter, elastic recoil detection analysis (ERDA), non-resonant nuclear reaction analysis (NRA), and particle induced X-ray emission (PIXE).
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Plasma operation with an all metal first-wall: Comparison of an ITER-like wall with a carbon wall in JET

TL;DR: 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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Q1. What contributions have the authors mentioned in the paper "Global erosion and deposition patterns in jet with the iter-like wall" ?

In this paper, a set of Be and W tiles removed after the first ITER-like wall campaigns ( JET-ILW ) from 2011-2012 was analyzed. 

During the divertor phase of each discharge erosion is probably dominated by charge exchange neutral (CXN) bombardment of the main chamber wall, and is followed by migration along the SOL to the inner divertor. 

After over two decades of JET operation with a carbon wall, the ITER-like wall project at JET (JET-ILW) was initiated to explore plasma performance and plasma-wall interaction processes with a full metal wall: bulk beryllium (Be), Be-coated Inconel in the main chamber and bulk tungsten (W) or W-coated carbon fibre composites (CFC) in the divertor [1, 2]. 

Experimental data were processed using NDF [10] and/or SIMNRA [11] software to determine the chemical composition and thickness of deposits. 

The amount of material deposited on Tiles 4 and 6 was generally below ~2.5·1018 at/cm2, however areas of highier deposition (~6·1018 at/cm2 of Be over the 1 mm2 beam area) were found on the slopping of these tiles. 

The tiles are relatively clean, however there are traces of W, Ni, Mo, Cr, and Fe on the surface, and NRA shows some D retention. 

This is evidenced by erosion measurements at the Inner Wall Cladding (IWC) tiles that line the vessel wall between the IWGL [14] which suggest that the IWC may account for a significant fraction of the Be deposition found in the divertor. 

There are also many areas where widespread arcing has occurred that are visible on Be tiles: such arcing may also be widespread on W-coated CFC tiles but would not be easily visible, however could easily dislodge coating asperities from these rough surfaces. 

Some contribution may also be expected from re-erosion of the deposits on the IWGL, which may have a higher erosion yield than the bulk material. 

combining the information of the BSE microscopy, the SEM analysis and IBA, it can be concluded that the deposited  material has a multi-layered structure consisting of an outer layer of pure