This title appears in the Scientific Report :
2009
Please use the identifier:
http://dx.doi.org/10.1016/j.nimb.2008.11.035 in citations.
Analysis of fuel retention in plasma-facing components from controlled fusion devices
Analysis of fuel retention in plasma-facing components from controlled fusion devices
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...
Saved in:
Personal Name(s): | Rubel, M. |
---|---|
Coad, J.P. / Likonen, J. / Philipps, V. | |
Contributing Institute: |
Plasmaphysik; IEF-4 |
Published in: | Nuclear instruments & methods in physics research / B, 267 (2009) S. 711 - 717 |
Imprint: |
Amsterdam [u.a.]
Elsevier
2009
|
Physical Description: |
711 - 717 |
DOI: |
10.1016/j.nimb.2008.11.035 |
Document Type: |
Journal Article |
Research Program: |
Fusion |
Series Title: |
Nuclear Instruments and Methods in Physics Research Section B
267 |
Subject (ZB): | |
Publikationsportal JuSER |
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. (C) 2008 EURATOM. Published by Elsevier B.V. All rights reserved. |