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^*, 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

^*Corresponding author for this work

Hydrogen Isotope Research Center, Organization for Promotion of Research

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

8 Scopus citations

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
State	Published - 2020/11

Keywords

Beryllium
ITER-like wall
Joint European Torus
Radiography
Tritium analysis

ASJC Scopus subject areas

Civil and Structural Engineering
Nuclear Energy and Engineering
General Materials Science
Mechanical Engineering

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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, Article 111959. https://doi.org/10.1016/j.fusengdes.2020.111959

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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",

note = "Publisher Copyright: {\textcopyright} 2020 The Author(s)",

year = "2020",

month = nov,

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

language = "英語",

volume = "160",

journal = "Fusion Engineering and Design",

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publisher = "Elsevier B.V.",

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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

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 - 2020/11

Y1 - 2020/11

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

UR - http://www.scopus.com/inward/record.url?scp=85090038832&partnerID=8YFLogxK

U2 - 10.1016/j.fusengdes.2020.111959

DO - 10.1016/j.fusengdes.2020.111959

M3 - 学術論文

AN - SCOPUS:85090038832

SN - 0920-3796

VL - 160

JO - Fusion Engineering and Design

JF - Fusion Engineering and Design

M1 - 111959

ER -

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

Keywords

ASJC Scopus subject areas

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