Analysis of fuel retention in plasma-facing components from controlled fusion devices

M. Rubel (Corresponding Author), J. P. Coad, Jari Likonen, V. Philipps, JET-EFDA Contributors

Research output: Contribution to journalArticleScientificpeer-review

14 Citations (Scopus)

Abstract

First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma–wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.
Original languageEnglish
Pages (from-to)711-717
Number of pages7
JournalNuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms
Volume267
Issue number4
DOIs
Publication statusPublished - 2009
MoE publication typeA1 Journal article-refereed
Event17th International Workshop on Inelastic Ion-Surface Collisions - Porquerolles, France
Duration: 21 Sep 200826 Sep 2008

Fingerprint

controlled fusion
Facings
Fusion reactions
Plasmas
Surface analysis
Beam plasma interactions
high temperature plasmas
Ion beams
erosion
Erosion
ion beams
interactions

Keywords

  • Controlled thermonuclear fusion
  • Wall materials
  • Retention
  • Deuterium
  • Tokamak

Cite this

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title = "Analysis of fuel retention in plasma-facing components from controlled fusion devices",
abstract = "First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma–wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.",
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Analysis of fuel retention in plasma-facing components from controlled fusion devices. / Rubel, M. (Corresponding Author); Coad, J. P.; Likonen, Jari; Philipps, V.; JET-EFDA Contributors.

In: Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms, Vol. 267, No. 4, 2009, p. 711-717.

Research output: Contribution to journalArticleScientificpeer-review

TY - JOUR

T1 - Analysis of fuel retention in plasma-facing components from controlled fusion devices

AU - Rubel, M.

AU - Coad, J. P.

AU - Likonen, Jari

AU - Philipps, V.

AU - JET-EFDA Contributors, null

PY - 2009

Y1 - 2009

N2 - First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma–wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.

AB - First wall components in controlled fusion devices undergo severe modification by various physical and chemical processes arising from plasma–wall interactions: material erosion, its transport in the plasma and re-deposition. The intention of this work is to give a concise overview of key issues in the characterization of plasma-facing materials and components in tokamaks. The importance of surface analysis in studies of fuel inventory and material migration is presented. Experimental procedures and analysis methods are briefly reviewed with emphasis on ion beam techniques which play a prominent role in studies of wall components exposed to hot plasmas. Practical aspects in the analytical approach are addressed and special instrumentation used in these studies is described.

KW - Controlled thermonuclear fusion

KW - Wall materials

KW - Retention

KW - Deuterium

KW - Tokamak

U2 - 10.1016/j.nimb.2008.11.035

DO - 10.1016/j.nimb.2008.11.035

M3 - Article

VL - 267

SP - 711

EP - 717

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 - 4

ER -