Abstract
The divertor surfaces in JET with ITER-like wall (ILW)
have been studied using micro ion beam analysis
(u-IBA) methods and scanning electron microscopy (SEM).
Deposited layers with beryllium as main
constituent had been formed during plasma operations
through 2011-2012. The deuterium trapping
and impurity deposition were non-uniform, frequently
enhanced within pits, cracks and valleys, regions
reaching in size from 10 um to 200 um. The impurity
deposition and fuel retention were correlated with
the surface slope with respect to the direction of ion
incidence. Typically more than 70% of the total
measured areal density of trapped D was found in less
than 30% of the surface area. This is of consequence
for the interpretation of other surface analyses and in
extrapolation from fuel retention in JET with ITERlike
wall and rough divertor surfaces to ITER with smoother
surfaces.
| Original language | English |
|---|---|
| Pages (from-to) | 956-960 |
| Journal | Journal of Nuclear Materials |
| Volume | 463 |
| DOIs | |
| Publication status | Published - 2015 |
| MoE publication type | A1 Journal article-refereed |
UN SDGs
This output contributes to the following UN Sustainable Development Goals (SDGs)
-
SDG 7 Affordable and Clean Energy
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