Abstract
Tritium (T) distribution on the plasma-facing surfaces (PFSs) and inside castellation of Be limiter tiles from the JET tokamak with the ITER-like wall (ILW) was analyzed using imaging plate (IP) technique and β-ray induced X-ray spectrometry (BIXS). Regarding to PFSs, the outer poloidal limiter (OPL) showed significantly higher T concentrations than the inner wall guard limiter (IWGL) and upper dump plate (DP). The concentration of T on OPL was high at the central part. However, deuterium (D) and metallic impurities showed maximum concentration at the edges. This difference in distributions indicated different deposition and retention mechanisms between T and D. In contrast, deposition profiles of T concentrations on the castellated surfaces extended up to ∼ 5 mm into the gap, i.e. were similar to those of D and metallic impurities found by ion beam analysis.
Original language | English |
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Article number | 111959 |
Journal | Fusion Engineering and Design |
Volume | 160 |
Early online date | 1 Sept 2020 |
DOIs | |
Publication status | Published - Nov 2020 |
MoE publication type | A1 Journal article-refereed |
Funding
This work has been carried out within the framework of the EUROfusion Consortium and has received funding from the Euratom research and training programme 2014-2018 and 2019-2020 under grant agreement No 633053. The study was supported by JSPS KAKENHI (Grant no. JP26289353), the ITER Broader Approach Activities, and the National Institute for Fusion Research (NIFS) as a part of PWI Collaboration.
Keywords
- Beryllium
- ITER-like wall
- Joint European Torus
- Radiography
- Tritium analysis