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Comparison of Hydrogen Isotope Retention in Divertor Tiles of JET with ITER-Like Wall Exposed during 2011- 2012 and 2015-2016 Campaigns

https://repo.qst.go.jp/records/79428
https://repo.qst.go.jp/records/79428
e4fb5d3b-449e-4606-9292-a78f0c0def77
Item type 会議発表用資料 / Presentation(1)
公開日 2020-03-13
タイトル
タイトル Comparison of Hydrogen Isotope Retention in Divertor Tiles of JET with ITER-Like Wall Exposed during 2011- 2012 and 2015-2016 Campaigns
言語
言語 eng
資源タイプ
資源タイプ識別子 http://purl.org/coar/resource_type/c_c94f
資源タイプ conference object
アクセス権
アクセス権 metadata only access
アクセス権URI http://purl.org/coar/access_right/c_14cb
著者 Oya, Yasuhisa

× Oya, Yasuhisa

WEKO 853088

Oya, Yasuhisa

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Masuzaki, Suguru

× Masuzaki, Suguru

WEKO 853089

Masuzaki, Suguru

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Tokitani, Masayuki

× Tokitani, Masayuki

WEKO 853090

Tokitani, Masayuki

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Nakata, Moeko

× Nakata, Moeko

WEKO 853091

Nakata, Moeko

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Sun, Fei

× Sun, Fei

WEKO 853092

Sun, Fei

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Oyaizu, Makoto

× Oyaizu, Makoto

WEKO 853093

Oyaizu, Makoto

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Isobe, Kanetsugu

× Isobe, Kanetsugu

WEKO 853094

Isobe, Kanetsugu

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Asakura, Nobuyuki

× Asakura, Nobuyuki

WEKO 853095

Asakura, Nobuyuki

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Otsuka, Teppei

× Otsuka, Teppei

WEKO 853096

Otsuka, Teppei

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M. Widdowson, Anna

× M. Widdowson, Anna

WEKO 853097

M. Widdowson, Anna

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Likonen, Jari

× Likonen, Jari

WEKO 853098

Likonen, Jari

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Rubel, Marek

× Rubel, Marek

WEKO 853099

Rubel, Marek

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Oyaizu, Makoto

× Oyaizu, Makoto

WEKO 853100

en Oyaizu, Makoto

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Isobe, Kanetsugu

× Isobe, Kanetsugu

WEKO 853101

en Isobe, Kanetsugu

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Asakura, Nobuyuki

× Asakura, Nobuyuki

WEKO 853102

en Asakura, Nobuyuki

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抄録
内容記述タイプ Abstract
内容記述 Evaluation of hydrogen isotopes retention in the plasma-facing components (PFC)l is required for the design of a future fusion reactor. To obtain a set of relevant data on the isotope retention and their surface state (and chemistry), the analysis of PFC from the JET tokamak with the ITER-Like Wall (JET-ILW) is both useful and important.
In previous studies, the correlation of surface chemical states and hydrogen isotope retention in the divertor samples from the first ILW campaign (ILW-1, 2011-2012, 19 h plasma operation, total energy 150 GJ) was determined. It was found that the major D desorption peaks were found at 643 K and 803 K. For samples at the strike point region, the D desorption temperature was clearly shifted towards higher T, indicating the stabilization of D trapping by higher heat load.
In this work, the studied tiles were exposed during the 3rd campaign (ILW-3) which comprised in total 23 h of plasma with the total energy input of 245 GJ. The hydrogen isotope retention and chemical states of divertor tiles were studied by thermal desorption spectroscopy (TDS) and X-ray photoelectron spectroscopy (XPS).
It was found that the major D desorption were located at 620 K and 800 K, which were consistent with the data for ILW-1. However, the total D retention was increased. The XPS analysis showed that major elements on the surface was Be with forming oxide state with co-existence of W. Carbon was found mainly on the outer divertor tiles.
In the presentation, detailed XPS and TDS results will be shown and discuss the hydrogen isotope retention behavior in JET-ILW divertor tiles.
会議概要(会議名, 開催地, 会期, 主催者等)
内容記述タイプ Other
内容記述 12 th International Conference on Tritium Science & Technology
発表年月日
日付 2019-04-22
日付タイプ Issued
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