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

M. Rubel; J.P. Coad; Jari Likonen; V. Philipps; JET-EFDA contributors

doi:10.1016/j.nimb.2008.11.035

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

M. Rubel^*
, J.P. Coad
, Jari Likonen
, V. Philipps
, JET-EFDA contributors

^*Corresponding author for this work

KTH Royal Institute of Technology
National Nuclear Laboratory (Abingdon)
Forschungszentrum Jülich GmbH (FZJ)

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

19 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 language	English
Pages (from-to)	711-717
Journal	Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms
Volume	267
Issue number	4
DOIs	https://doi.org/10.1016/j.nimb.2008.11.035
Publication status	Published - 2009
MoE publication type	A1 Journal article-refereed
Event	17th International Workshop on Inelastic Ion-Surface Collisions - Porquerolles, France Duration: 21 Sept 2008 → 26 Sept 2008

UN SDGs

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

SDG 7 Affordable and Clean Energy

Keywords

Controlled thermonuclear fusion
Wall materials
Retention
Deuterium
Tokamak

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10.1016/j.nimb.2008.11.035

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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.",

keywords = "Controlled thermonuclear fusion, Wall materials, Retention, Deuterium, Tokamak",

author = "M. Rubel and J.P. Coad and Jari Likonen and V. Philipps and \{JET-EFDA contributors\}",

year = "2009",

doi = "10.1016/j.nimb.2008.11.035",

language = "English",

volume = "267",

pages = "711--717",

journal = "Nuclear Instruments and Methods in Physics Research. Section B: Beam Interactions with Materials and Atoms",

issn = "0168-583X",

publisher = "Elsevier",

number = "4",

note = "17th International Workshop on Inelastic Ion-Surface Collisions, IISC-17 ; Conference date: 21-09-2008 Through 26-09-2008",

}

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

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

SN - 0168-583X

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

IS - 4

T2 - 17th International Workshop on Inelastic Ion-Surface Collisions

Y2 - 21 September 2008 through 26 September 2008

ER -

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

Abstract

UN SDGs

Keywords

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