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

S.E. Lee; Y. Hatano; 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

doi:10.1016/j.nme.2021.100930

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

S.E. Lee
, Y. Hatano^*
, 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

^*Corresponding author for this work

University of Toyama
National Institute for Fusion Science
Shizuoka University
Kindai University
Ibaraki University
National Institutes for Quantum Science and Technology (QST)
Culham Science Centre
École Royale Militaire
KTH Royal Institute of Technology

Research output: Contribution to journal › Article › Scientific › peer-review

11 Citations (Scopus)

Abstract

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 language	English
Article number	100930
Journal	Nuclear Materials and Energy
Volume	26
DOIs	https://doi.org/10.1016/j.nme.2021.100930
Publication status	Published - 2021
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 the ITER Broader Approach Activities and JSPS KAKENHI (Grant No. JP26289353).

UN SDGs

This output contributes to the following UN Sustainable Development Goals (SDGs)

SDG 7 Affordable and Clean Energy

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Lee, S. E., Hatano, Y., Tokitani, M., Mazusaki, S., Oya, Y., Otsuka, T., Ashikawa, N., Torikai, Y., Asakura, N., Nakamura, H., Isobe, K., Kurotaki, H., Hamaguchi, D., Hayashi, T., Widdowson, A., Jachmich, S., Likonen, J., & Rubel, M. (2021). Global distribution of tritium in JET with the ITER-like wall. Nuclear Materials and Energy, 26, Article 100930. https://doi.org/10.1016/j.nme.2021.100930

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title = "Global distribution of tritium in JET with the ITER-like wall",

abstract = "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.",

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

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Lee, SE, Hatano, Y, Tokitani, M, Mazusaki, S, Oya, Y, Otsuka, T, Ashikawa, N, Torikai, Y, Asakura, N, Nakamura, H, Isobe, K, Kurotaki, H, Hamaguchi, D, Hayashi, T, Widdowson, A, Jachmich, S, Likonen, J & Rubel, M 2021, 'Global distribution of tritium in JET with the ITER-like wall', Nuclear Materials and Energy, vol. 26, 100930. https://doi.org/10.1016/j.nme.2021.100930

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T1 - Global distribution of tritium in JET with the ITER-like wall

AU - Lee, S.E.

AU - Hatano, Y.

AU - Tokitani, Masayuki

AU - Mazusaki, S.

AU - Oya, Yasuhisa

AU - Otsuka, Teppei

AU - Ashikawa, N.

AU - Torikai, Y.

AU - Asakura, Nobuyuki

AU - Nakamura, H.

AU - Isobe, K.

AU - Kurotaki, H.

AU - Hamaguchi, D.

AU - Hayashi, T.

AU - Widdowson, Anna

AU - Jachmich, S.

AU - Likonen, Jari

AU - Rubel, M.

PY - 2021

Y1 - 2021

N2 - 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.

AB - 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.

UR - https://www.scopus.com/pages/publications/85100584134

U2 - 10.1016/j.nme.2021.100930

DO - 10.1016/j.nme.2021.100930

M3 - Article

SN - 2352-1791

VL - 26

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

M1 - 100930

ER -

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

Abstract

Funding

UN SDGs

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