Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry

S. E. Lee; Y. Hatano; M. Hara; S. Masuzaki; M. Tokitani; M. Oyaizu; H. Kurotaki; D. Hamaguchi; H. Nakamura; N. Asakura; Y. Oya; J. Likonen; A. Widdowson; S. Jachmich; K. Helariutta; M. Rubel

doi:10.1016/j.fusengdes.2020.111959

Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry

S. E. Lee (Corresponding Author), Y. Hatano, M. Hara, S. Masuzaki, M. Tokitani, M. Oyaizu, H. Kurotaki, D. Hamaguchi, H. Nakamura, N. Asakura, Y. Oya, J. Likonen, A. Widdowson, S. Jachmich, K. Helariutta, M. Rubel

BA2F06 Fusion energy and decommissioning

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

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
Article number	111959
Journal	Fusion Engineering and Design
Volume	160
DOIs	https://doi.org/10.1016/j.fusengdes.2020.111959
Publication status	E-pub ahead of print - 1 Sep 2020
MoE publication type	A1 Journal article-refereed

Keywords

Beryllium
ITER-like wall
Joint European Torus
Radiography
Tritium analysis

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10.1016/j.fusengdes.2020.111959

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Lee, S. E., Hatano, Y., Hara, M., Masuzaki, S., Tokitani, M., Oyaizu, M., Kurotaki, H., Hamaguchi, D., Nakamura, H., Asakura, N., Oya, Y., Likonen, J., Widdowson, A., Jachmich, S., Helariutta, K., & Rubel, M. (2020). Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry. Fusion Engineering and Design, 160, [111959]. https://doi.org/10.1016/j.fusengdes.2020.111959

Lee, S. E. ; Hatano, Y. ; Hara, M. ; Masuzaki, S. ; Tokitani, M. ; Oyaizu, M. ; Kurotaki, H. ; Hamaguchi, D. ; Nakamura, H. ; Asakura, N. ; Oya, Y. ; Likonen, J. ; Widdowson, A. ; Jachmich, S. ; Helariutta, K. ; Rubel, M. / Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry. In: Fusion Engineering and Design. 2020 ; Vol. 160.

@article{cac2878f4c214c3989d21530f1d8f650,

title = "Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry",

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.",

keywords = "Beryllium, ITER-like wall, Joint European Torus, Radiography, Tritium analysis",

author = "Lee, {S. E.} and Y. Hatano and M. Hara and S. Masuzaki and M. Tokitani and M. Oyaizu and H. Kurotaki and D. Hamaguchi and H. Nakamura and N. Asakura and Y. Oya and J. Likonen and A. Widdowson and S. Jachmich and K. Helariutta and M. Rubel",

year = "2020",

month = sep,

day = "1",

doi = "10.1016/j.fusengdes.2020.111959",

language = "English",

volume = "160",

journal = "Fusion Engineering and Design",

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Lee, SE, Hatano, Y, Hara, M, Masuzaki, S, Tokitani, M, Oyaizu, M, Kurotaki, H, Hamaguchi, D, Nakamura, H, Asakura, N, Oya, Y, Likonen, J, Widdowson, A, Jachmich, S, Helariutta, K & Rubel, M 2020, 'Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry', Fusion Engineering and Design, vol. 160, 111959. https://doi.org/10.1016/j.fusengdes.2020.111959

Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry. / Lee, S. E. (Corresponding Author); Hatano, Y.; Hara, M.; Masuzaki, S.; Tokitani, M.; Oyaizu, M.; Kurotaki, H.; Hamaguchi, D.; Nakamura, H.; Asakura, N.; Oya, Y.; Likonen, J.; Widdowson, A.; Jachmich, S.; Helariutta, K.; Rubel, M.

In: Fusion Engineering and Design, Vol. 160, 111959, 01.09.2020.

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

TY - JOUR

T1 - Tritium distribution analysis of Be limiter tiles from JET-ITER like wall campaigns using imaging plate technique and β-ray induced X-ray spectrometry

AU - Lee, S. E.

AU - Hatano, Y.

AU - Hara, M.

AU - Masuzaki, S.

AU - Tokitani, M.

AU - Oyaizu, M.

AU - Kurotaki, H.

AU - Hamaguchi, D.

AU - Nakamura, H.

AU - Asakura, N.

AU - Oya, Y.

AU - Likonen, J.

AU - Widdowson, A.

AU - Jachmich, S.

AU - Helariutta, K.

AU - Rubel, M.

PY - 2020/9/1

Y1 - 2020/9/1

N2 - 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.

AB - 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.

KW - Beryllium

KW - ITER-like wall

KW - Joint European Torus

KW - Radiography

KW - Tritium analysis

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U2 - 10.1016/j.fusengdes.2020.111959

DO - 10.1016/j.fusengdes.2020.111959

M3 - Article

AN - SCOPUS:85090038832

VL - 160

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

SN - 0920-3796

M1 - 111959

ER -