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. プロシーディングス

The Accomplishments of Lithium Target and Test Facility Validation Activities in the IFMIF/EVEDA Phase

https://repo.qst.go.jp/records/54742
https://repo.qst.go.jp/records/54742
07fbc589-3694-43c5-b09c-21e2ce5cc388
Item type 会議発表論文 / Conference Paper(1)
公開日 2017-03-28
タイトル
タイトル The Accomplishments of Lithium Target and Test Facility Validation Activities in the IFMIF/EVEDA Phase
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_5794
資源タイプ conference paper
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 Arbeiter, Frederik

× Arbeiter, Frederik

WEKO 559611

Arbeiter, Frederik

Search repository
近藤, 浩夫

× 近藤, 浩夫

WEKO 559612

近藤, 浩夫

Search repository
大平, 茂

× 大平, 茂

WEKO 559613

大平, 茂

Search repository
他

× 他

WEKO 559614

他

Search repository
近藤 浩夫

× 近藤 浩夫

WEKO 559615

en 近藤 浩夫

Search repository
大平 茂

× 大平 茂

WEKO 559616

en 大平 茂

Search repository
抄録
内容記述タイプ Abstract
内容記述 As part of the Engineering Validation and Engineering Design Activities (EVEDA) phase for the International Fusion Materials Irradiation Facility IFMIF, major elements of Lithium Target Facility and the Test Facility were designed, prototyped and validated. For the Lithium Target Facility, the ELTL lithium loop was built and used to test the stability (waves and long term) of the lithium flow in the target, work out the startup procedures, and test lithium purification and analysis. It was confirmed by experiments in the Lifus 6 plant, that Lithium corrosion on ferritic martensitic steels is acceptably low. Furthermore, complex remote handling procedures for the remote maintenance of the target in the Test Cell environment were successfully practiced. For the Test Facility, two variants of a High Flux Test Module were prototyped and tested in helium loops, demonstrating their good capabilities of maintaining the material specimens at the desired temperature with a low temperature spread. Irradiation tests were performed for heated specimen capsules and irradiation instrumentation in the BR2 reactor. The Small Specimen Test Technique (SSTT), essential for obtaining material test results with limited irradiation volume, was advanced by evaluating specimen shape and test technique influences.
書誌情報 Proc. of the 26th IAEA Fusion Energy Conference (IAEA-FEC2016)

発行日 2017-03
戻る
0
views
See details
Views

Versions

Ver.1 2023-05-15 22:57:19.049058
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