Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall

Y. Zhou; H. Bergsåker; I. Bykov; P. Petersson; G. Possnert; Jari Likonen; J. Pettersson; Seppo Koivuranta; A. Widdowson; JET Contributors

doi:10.1016/j.nme.2017.02.015

Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall

Y. Zhou
, H. Bergsåker
, I. Bykov
, P. Petersson
, G. Possnert
, Jari Likonen
, J. Pettersson
, Seppo Koivuranta
, A. Widdowson
, JET Contributors

Research output: Contribution to journal › Article › Scientific › peer-review

6 Citations (Scopus)

Abstract

In JET with ITER-like wall, beryllium eroded in the main chamber is transported to the divertor and deposited mainly at the horizontal surfaces of tiles 1 and 0 (high field gap closure, HFGC). These surfaces are tungsten coated carbon fibre composite (CFC). Surface sampleswere collected following the plasma operations in 2011-2012 and 2013-2014 respectively. The surfaces, as well as polished cross sections of the deposited layers at the surfaces have been studied with micro ion beam analysis methods (µ-IBA).Deposition of Beand other impurities, and retention of D is microscopically inhomogeneous. Impurities and trapped deuterium accumulate preferentially in cracks, pits and depressed regions, and at the sides of large pits in the substrate (e.g. arc tracks where the W coating has been removed). With careful overlaying of µ-NRA elemental maps with optical microscopy images, it is possible to separate surface roughness effects from depth profiles at microscopically flat surface regions.

Original language	English
Pages (from-to)	412-417
Journal	Nuclear Materials and Energy
Volume	12
Early online date	2017
DOIs	https://doi.org/10.1016/j.nme.2017.02.015
Publication status	Published - 1 Aug 2017
MoE publication type	A1 Journal article-refereed
Event	22nd International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI-22) - Rome, Italy Duration: 30 May 2016 → 3 Jun 2016

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This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

Keywords

carbon
carbon fibers
fusion reactor divertors
Ion beams
surface roughness
deposited layer
elemental maps
flat surfaces
horizontal surfaces
Ion beam analysis
plasma operations
surface roughness effects
tungsten coated carbon

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10.1016/j.nme.2017.02.015Licence: CC BY-NC-ND

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@article{271857e86a634978a4ef94874292210c,

title = "Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall",

abstract = "In JET with ITER-like wall, beryllium eroded in the main chamber is transported to the divertor and deposited mainly at the horizontal surfaces of tiles 1 and 0 (high field gap closure, HFGC). These surfaces are tungsten coated carbon fibre composite (CFC). Surface sampleswere collected following the plasma operations in 2011-2012 and 2013-2014 respectively. The surfaces, as well as polished cross sections of the deposited layers at the surfaces have been studied with micro ion beam analysis methods (µ-IBA).Deposition of Beand other impurities, and retention of D is microscopically inhomogeneous. Impurities and trapped deuterium accumulate preferentially in cracks, pits and depressed regions, and at the sides of large pits in the substrate (e.g. arc tracks where the W coating has been removed). With careful overlaying of µ-NRA elemental maps with optical microscopy images, it is possible to separate surface roughness effects from depth profiles at microscopically flat surface regions.",

keywords = "carbon, carbon fibers, fusion reactor divertors, Ion beams, surface roughness, deposited layer, elemental maps, flat surfaces, horizontal surfaces, Ion beam analysis, plasma operations, surface roughness effects, tungsten coated carbon",

author = "Y. Zhou and H. Bergs{\aa}ker and I. Bykov and P. Petersson and G. Possnert and Jari Likonen and J. Pettersson and Seppo Koivuranta and A. Widdowson and \{JET Contributors\}",

year = "2017",

month = aug,

day = "1",

doi = "10.1016/j.nme.2017.02.015",

language = "English",

volume = "12",

pages = "412--417",

journal = "Nuclear Materials and Energy",

issn = "2352-1791",

publisher = "Elsevier",

note = "22nd International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI-22), PSI-22 ; Conference date: 30-05-2016 Through 03-06-2016",

}

TY - JOUR

T1 - Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall

AU - Zhou, Y.

AU - Bergsåker, H.

AU - Bykov, I.

AU - Petersson, P.

AU - Possnert, G.

AU - Likonen, Jari

AU - Pettersson, J.

AU - Koivuranta, Seppo

AU - Widdowson, A.

AU - JET Contributors

PY - 2017/8/1

Y1 - 2017/8/1

N2 - In JET with ITER-like wall, beryllium eroded in the main chamber is transported to the divertor and deposited mainly at the horizontal surfaces of tiles 1 and 0 (high field gap closure, HFGC). These surfaces are tungsten coated carbon fibre composite (CFC). Surface sampleswere collected following the plasma operations in 2011-2012 and 2013-2014 respectively. The surfaces, as well as polished cross sections of the deposited layers at the surfaces have been studied with micro ion beam analysis methods (µ-IBA).Deposition of Beand other impurities, and retention of D is microscopically inhomogeneous. Impurities and trapped deuterium accumulate preferentially in cracks, pits and depressed regions, and at the sides of large pits in the substrate (e.g. arc tracks where the W coating has been removed). With careful overlaying of µ-NRA elemental maps with optical microscopy images, it is possible to separate surface roughness effects from depth profiles at microscopically flat surface regions.

AB - In JET with ITER-like wall, beryllium eroded in the main chamber is transported to the divertor and deposited mainly at the horizontal surfaces of tiles 1 and 0 (high field gap closure, HFGC). These surfaces are tungsten coated carbon fibre composite (CFC). Surface sampleswere collected following the plasma operations in 2011-2012 and 2013-2014 respectively. The surfaces, as well as polished cross sections of the deposited layers at the surfaces have been studied with micro ion beam analysis methods (µ-IBA).Deposition of Beand other impurities, and retention of D is microscopically inhomogeneous. Impurities and trapped deuterium accumulate preferentially in cracks, pits and depressed regions, and at the sides of large pits in the substrate (e.g. arc tracks where the W coating has been removed). With careful overlaying of µ-NRA elemental maps with optical microscopy images, it is possible to separate surface roughness effects from depth profiles at microscopically flat surface regions.

KW - carbon

KW - carbon fibers

KW - fusion reactor divertors

KW - Ion beams

KW - surface roughness

KW - deposited layer

KW - elemental maps

KW - flat surfaces

KW - horizontal surfaces

KW - Ion beam analysis

KW - plasma operations

KW - surface roughness effects

KW - tungsten coated carbon

UR - https://www.scopus.com/pages/publications/85015310440

U2 - 10.1016/j.nme.2017.02.015

DO - 10.1016/j.nme.2017.02.015

M3 - Article

SN - 2352-1791

VL - 12

SP - 412

EP - 417

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

T2 - 22nd International Conference on Plasma-Surface Interactions in Controlled Fusion Devices (PSI-22)

Y2 - 30 May 2016 through 3 June 2016

ER -

Microanalysis of deposited layers in the inner divertor of JET with ITER-like wall

Abstract

UN SDGs

Keywords

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