Global distribution of tritium in JET with the ITER-like wall

S.E. Lee, Y. Hatano (Corresponding Author), Masayuki Tokitani, S. Mazusaki, Yasuhisa Oya, Teppei Otsuka, N. Ashikawa, Y. Torikai, Nobuyuki Asakura, H. Nakamura, K. Isobe, H. Kurotaki, D. Hamaguchi, T. Hayashi, Anna Widdowson, S. Jachmich, Jari Likonen, M. Rubel

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Nondestructive analysis of tritium (T) distribution was performed by means of imaging plate technique on specimens cut from the Be limiters, W-coated carbon tiles and bulk W lamellae retrieved from the JET tokamak after the first and third experimental campaigns with the ITER-like wall. Afterwards, analyses were continued using X-ray photoelectron spectroscopy, microscopy techniques and thermal desorption spectroscopy. Co-deposits formed on the W-coated tiles in the 1st campaign showed large T retention because of high carbon content reaching up to 50 atomic %, while the carbon fraction in co-deposits after the 3rd campaign was distinctly lower. The T retention of the plasma-facing surface of the bulk W tile was smaller than that of the W-coated tiles by a factor of 20, while deposition of small amount of T was found at the side surfaces facing to the gaps in a lamella structure. The correlation of T distributions with surface morphology and the discharge conditions is discussed.
Original languageEnglish
Article number100930
JournalNuclear Materials and Energy
Publication statusPublished - 2021
MoE publication typeA1 Journal article-refereed


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 views and opinions expressed herein do not necessarily reflect those of the European Commission. The study was supported by the ITER Broader Approach Activities and JSPS KAKENHI (Grant No. JP26289353).


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