Erosion and re-deposition processes in JET tiles studied with ion beams

L. C. Alves (Corresponding Author), E. Alves, N. P. Barradas, R. Mateus, P. Carvalho, J. P. Coad, A. M. Widdowson, Jari Likonen, Seppo Koivuranta

Research output: Contribution to journalArticleScientificpeer-review

13 Citations (Scopus)

Abstract

Plasma facing components in fusion reactor chambers will operate under extreme conditions. Among the processes with implications on the material lifetime are erosion and re-deposition due to plasma interactions. This work will address the behaviour of both JET divertor and outer poloidal limiters (OPL) under plasma irradiation. The limiters comprise about 50 pairs of tiles in a poloidal stack, each of which has a plasma facing surface about 25 mm (poloidal) by 350 mm (toroidal) and is about 50 mm thick. The divertor tiles are located at the bottom of the chamber and withstand high fluxes of radiation and heat. Standard carbon-fibre composite (CFC) tiles coated with a thin layer of W overlaid with a 10 μm layer of C were studied with RBS/PIXE to understand the erosion/re-deposition processes occurring in these regions of the reactor chamber. High resolution surface morphology was assessed through SEM with and without tilting of the sample. The retention of hydrogen isotopes in the tiles were studied combining NRA and ERDA techniques – this is mostly 2H from the fuelling gas, but 3H is also present as a result of 2H–2H fusion reactions, and 1H coming from the atmospheric exposure.

Original languageEnglish
Pages (from-to)1991-1996
Number of pages6
JournalNuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms
Volume268
Issue number11-12
DOIs
Publication statusPublished - 2010
MoE publication typeA1 Journal article-refereed
Event19th International Conference on Ion Beam Analysis, IBA 2009 - Cambridge, United Kingdom
Duration: 7 Sep 200911 Sep 2009

Fingerprint

tiles
Tile
Ion beams
erosion
Erosion
ion beams
chambers
Limiters
Plasmas
Plasma interactions
plasma interactions
Fueling
hydrogen isotopes
refueling
fusion reactors
fiber composites
Fusion reactors
carbon fibers
Carbon fibers
Isotopes

Keywords

  • Carbon-fibre composites tiles
  • Fusion reactor materials
  • Ion beam analysis

Cite this

Alves, L. C. ; Alves, E. ; Barradas, N. P. ; Mateus, R. ; Carvalho, P. ; Coad, J. P. ; Widdowson, A. M. ; Likonen, Jari ; Koivuranta, Seppo. / Erosion and re-deposition processes in JET tiles studied with ion beams. In: Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms. 2010 ; Vol. 268, No. 11-12. pp. 1991-1996.
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abstract = "Plasma facing components in fusion reactor chambers will operate under extreme conditions. Among the processes with implications on the material lifetime are erosion and re-deposition due to plasma interactions. This work will address the behaviour of both JET divertor and outer poloidal limiters (OPL) under plasma irradiation. The limiters comprise about 50 pairs of tiles in a poloidal stack, each of which has a plasma facing surface about 25 mm (poloidal) by 350 mm (toroidal) and is about 50 mm thick. The divertor tiles are located at the bottom of the chamber and withstand high fluxes of radiation and heat. Standard carbon-fibre composite (CFC) tiles coated with a thin layer of W overlaid with a 10 μm layer of C were studied with RBS/PIXE to understand the erosion/re-deposition processes occurring in these regions of the reactor chamber. High resolution surface morphology was assessed through SEM with and without tilting of the sample. The retention of hydrogen isotopes in the tiles were studied combining NRA and ERDA techniques – this is mostly 2H from the fuelling gas, but 3H is also present as a result of 2H–2H fusion reactions, and 1H coming from the atmospheric exposure.",
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Erosion and re-deposition processes in JET tiles studied with ion beams. / Alves, L. C. (Corresponding Author); Alves, E.; Barradas, N. P.; Mateus, R.; Carvalho, P.; Coad, J. P.; Widdowson, A. M.; Likonen, Jari; Koivuranta, Seppo.

In: Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms, Vol. 268, No. 11-12, 2010, p. 1991-1996.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Erosion and re-deposition processes in JET tiles studied with ion beams

AU - Alves, L. C.

AU - Alves, E.

AU - Barradas, N. P.

AU - Mateus, R.

AU - Carvalho, P.

AU - Coad, J. P.

AU - Widdowson, A. M.

AU - Likonen, Jari

AU - Koivuranta, Seppo

PY - 2010

Y1 - 2010

N2 - Plasma facing components in fusion reactor chambers will operate under extreme conditions. Among the processes with implications on the material lifetime are erosion and re-deposition due to plasma interactions. This work will address the behaviour of both JET divertor and outer poloidal limiters (OPL) under plasma irradiation. The limiters comprise about 50 pairs of tiles in a poloidal stack, each of which has a plasma facing surface about 25 mm (poloidal) by 350 mm (toroidal) and is about 50 mm thick. The divertor tiles are located at the bottom of the chamber and withstand high fluxes of radiation and heat. Standard carbon-fibre composite (CFC) tiles coated with a thin layer of W overlaid with a 10 μm layer of C were studied with RBS/PIXE to understand the erosion/re-deposition processes occurring in these regions of the reactor chamber. High resolution surface morphology was assessed through SEM with and without tilting of the sample. The retention of hydrogen isotopes in the tiles were studied combining NRA and ERDA techniques – this is mostly 2H from the fuelling gas, but 3H is also present as a result of 2H–2H fusion reactions, and 1H coming from the atmospheric exposure.

AB - Plasma facing components in fusion reactor chambers will operate under extreme conditions. Among the processes with implications on the material lifetime are erosion and re-deposition due to plasma interactions. This work will address the behaviour of both JET divertor and outer poloidal limiters (OPL) under plasma irradiation. The limiters comprise about 50 pairs of tiles in a poloidal stack, each of which has a plasma facing surface about 25 mm (poloidal) by 350 mm (toroidal) and is about 50 mm thick. The divertor tiles are located at the bottom of the chamber and withstand high fluxes of radiation and heat. Standard carbon-fibre composite (CFC) tiles coated with a thin layer of W overlaid with a 10 μm layer of C were studied with RBS/PIXE to understand the erosion/re-deposition processes occurring in these regions of the reactor chamber. High resolution surface morphology was assessed through SEM with and without tilting of the sample. The retention of hydrogen isotopes in the tiles were studied combining NRA and ERDA techniques – this is mostly 2H from the fuelling gas, but 3H is also present as a result of 2H–2H fusion reactions, and 1H coming from the atmospheric exposure.

KW - Carbon-fibre composites tiles

KW - Fusion reactor materials

KW - Ion beam analysis

U2 - 10.1016/j.nimb.2010.02.115

DO - 10.1016/j.nimb.2010.02.115

M3 - Article

VL - 268

SP - 1991

EP - 1996

JO - Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms

JF - Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms

SN - 0168-583X

IS - 11-12

ER -