Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
1567512 | Journal of Nuclear Materials | 2009 | 4 Pages |
Abstract
Evolution of the ITER outer divertor target surface is analyzed for the case of wall-sputtered beryllium transported to an initially tungsten divertor. Coupled codes for the convective edge plasma, impurity transport, and mixed-surface sputtering, give the wall-source beryllium flux to the divertor, the sputtering erosion/redeposition response, and the resulting beryllium surface content/growth. The analysis shows zero net Be growth over most (â¼80%) of the divertor, due to high re-sputtering and reflection-with an equilibrium Be/W surface quickly formed (â¼10Â s)-but with a region near the strike point having substantial (â¼1Â nm/s) growth.
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Nuclear Energy and Engineering
Authors
J.N. Brooks, J.P. Allain,