Material erosion at the vessel walls of future fusion devices

For a next-step fusion device the erosion at the vessel walls during normal operation caused by the bombardment with different species from the plasma is estimated. The wall fluxes are calculated for a given ‘burning’ plasma with the computer code B2-EIRENE. With the known sputtering yields the eros...

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Bibliographic Details
Published inJournal of nuclear materials Vol. 313; no. Complete; pp. 388 - 392
Main Authors Behrisch, R., Federici, G., Kukushkin, A., Reiter, D.
Format Journal Article
LanguageEnglish
Published Elsevier B.V 01.03.2003
Subjects
Beryllium
Carbon
Sputtering
Tokamaks
Tungsten
52.55.Fa
C0100
T0100
T1000
Carbon
Sputtering
81.65.C
Tungsten
Beryllium
81.05.T
52.40.H
B0100
F0400
Tokamaks
28.52.Fa
S1300
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Summary:For a next-step fusion device the erosion at the vessel walls during normal operation caused by the bombardment with different species from the plasma is estimated. The wall fluxes are calculated for a given ‘burning’ plasma with the computer code B2-EIRENE. With the known sputtering yields the erosion rates for vessel walls made out of Be, C, Fe, Mo or W, are calculated. The erosion by ions is found to be of the same order of magnitude as the erosion by energetic neutrals. The erosion has minima around the area of gas feed and maxima close by and at the bottom near the baffles of the divertor. The calculated total erosion is of the order of 10 21 to 10 22 atom/s for low Z materials, and a factor 10–20 lower for high Z materials, such as W, resulting in about 5 kg per full-day of operation or 1 t/y.
Bibliography:ObjectType-Article-2
SourceType-Scholarly Journals-1
ObjectType-Feature-1
content type line 23
ISSN:0022-3115
1873-4820
DOI:10.1016/S0022-3115(02)01580-5