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; Jari 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
, Jari Likonen
, A. Widdowson
, S. Jachmich
, K. Helariutta
, M. Rubel

^*Corresponding author for this work

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

9 Citations (Scopus)

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
Early online date	1 Sept 2020
DOIs	https://doi.org/10.1016/j.fusengdes.2020.111959
Publication status	Published - Nov 2020
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 JSPS KAKENHI (Grant no. JP26289353), the ITER Broader Approach Activities, and the National Institute for Fusion Research (NIFS) as a part of PWI Collaboration.

Keywords

Beryllium
ITER-like wall
Joint European Torus
Radiography
Tritium analysis

UN SDGs

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

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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

@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 Jari Likonen and A. Widdowson and S. Jachmich and K. Helariutta and M. Rubel",

year = "2020",

month = nov,

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

language = "English",

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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, Jari

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 - https://www.scopus.com/pages/publications/85090038832

U2 - 10.1016/j.fusengdes.2020.111959

DO - 10.1016/j.fusengdes.2020.111959

M3 - Article

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

Funding

Keywords

UN SDGs

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