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 (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

BA2F06 Fusion energy and decommissioning

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

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

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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, [100930]. https://doi.org/10.1016/j.nme.2021.100930

Lee, S.E. ; Hatano, Y. ; Tokitani, Masayuki ; Mazusaki, S. ; Oya, Yasuhisa ; Otsuka, Teppei ; Ashikawa, N. ; Torikai, Y. ; Asakura, Nobuyuki ; Nakamura, H. ; Isobe, K. ; Kurotaki, H. ; Hamaguchi, D. ; Hayashi, T. ; Widdowson, Anna ; Jachmich, S. ; Likonen, Jari ; Rubel, M. / Global distribution of tritium in JET with the ITER-like wall. In: Nuclear Materials and Energy. 2021 ; Vol. 26.

@article{de53ea1f469c4b0ba76e1dfbb8201445,

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",

note = "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).",

year = "2021",

doi = "10.1016/j.nme.2021.100930",

language = "English",

volume = "26",

journal = "Nuclear Materials and Energy",

issn = "2352-1791",

publisher = "Elsevier",

}

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

Global distribution of tritium in JET with the ITER-like wall. / Lee, S.E.; Hatano, Y. (Corresponding Author); Tokitani, Masayuki ; Mazusaki, S.; Oya, Yasuhisa ; Otsuka, Teppei ; Ashikawa, N.; Torikai, Y.; Asakura, Nobuyuki ; Nakamura, H.; Isobe, K.; Kurotaki, H.; Hamaguchi, D.; Hayashi, T.; Widdowson, Anna; Jachmich, S.; Likonen, Jari; Rubel, M.

In: Nuclear Materials and Energy, Vol. 26, 100930, 2021.

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

TY - JOUR

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.

N1 - 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).

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.

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U2 - 10.1016/j.nme.2021.100930

DO - 10.1016/j.nme.2021.100930

M3 - Article

VL - 26

JO - Nuclear Materials and Energy

JF - Nuclear Materials and Energy

SN - 2352-1791

M1 - 100930

ER -