ログイン
言語:

WEKO3

  • トップ
  • ランキング
To
lat lon distance
To

Field does not validate



インデックスリンク

インデックスツリー

メールアドレスを入力してください。

WEKO

One fine body…

WEKO

One fine body…

アイテム

  1. 原著論文

The influence of the long-term heating under H2 atmosphere on the tritium release behavior from the neutron-irradiated Li2TiO3

https://repo.qst.go.jp/records/84700
https://repo.qst.go.jp/records/84700
91a41d00-2a3d-4ee6-b09d-aa11aa0f3d76
Item type 学術雑誌論文 / Journal Article(1)
公開日 2021-10-01
タイトル
タイトル The influence of the long-term heating under H2 atmosphere on the tritium release behavior from the neutron-irradiated Li2TiO3
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_6501
資源タイプ journal article
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 Akito, Ipponsugi

× Akito, Ipponsugi

WEKO 1022118

Akito, Ipponsugi

Search repository
Katayama, Kazunari

× Katayama, Kazunari

WEKO 1022119

Katayama, Kazunari

Search repository
Tsuyoshi, Hoshino

× Tsuyoshi, Hoshino

WEKO 1022120

Tsuyoshi, Hoshino

Search repository
Akito, Ipponsugi

× Akito, Ipponsugi

WEKO 1022121

en Akito, Ipponsugi

Search repository
Katayama, Kazunari

× Katayama, Kazunari

WEKO 1022122

en Katayama, Kazunari

Search repository
Tsuyoshi, Hoshino

× Tsuyoshi, Hoshino

WEKO 1022123

en Tsuyoshi, Hoshino

Search repository
抄録
内容記述タイプ Abstract
内容記述 Solid tritium breeding materials are expected to be used in high-temperature conditions for a long time in a fusion DEMO reactor. Thus, it is important to understand how bred tritium releases from the long-term heated material under the environment as close to a DEMO condition as possible to establish a tritium fuel cycle and keep it safe. In this work, the tritium release behavior from the irradiated Li2TiO3 pebbles that was preheated for 720 h at most was observed by heating at 1000 °C under 1000 Pa H2/Ar gas flow. The release peaks of HTO and HT were observed around 300 °C due to the desorption of the chemisorbed water. Also, the broad HTO peak was observed in a higher temperature region despite purging H2/Ar gas. This result suggests that this tritium was released without exchanging with H2 but with combining with oxygen in the pebbles. Moreover, the released tritium amount decreased as the pre-heating time. Finally, the amount of tritium that could not be released by the heating experiment was quantified by dissolving samples with an acid solution. Besides, the total tritium release ratio was discussed.
書誌情報 Fusion Engineering and Design

巻 170, p. 112495, 発行日 2021-09
ISSN
収録物識別子タイプ ISSN
収録物識別子 0920-3796
DOI
識別子タイプ DOI
関連識別子 10.1016/j.fusengdes.2021.112495
関連サイト
識別子タイプ DOI
関連識別子 https://doi.org/10.1016/j.fusengdes.2021.112495
戻る
0
views
See details
Views

Versions

Ver.1 2023-05-15 17:08:19.073929
Show All versions

Share

Mendeley Twitter Facebook Print Addthis

Cite as

エクスポート

OAI-PMH
  • OAI-PMH JPCOAR 2.0
  • OAI-PMH JPCOAR 1.0
  • OAI-PMH DublinCore
  • OAI-PMH DDI
Other Formats
  • JSON
  • BIBTEX

Confirm


Powered by WEKO3


Powered by WEKO3