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  1. Published Papers
  2. Published Papers

Potential of Copper Alloys using a Divertor Heat Sink in the Helical Reactor FFHR-d1 and their Brazing Properties with Tungsten Armor by using the Typical Candidate Filler Materials

http://hdl.handle.net/10655/00013369
http://hdl.handle.net/10655/00013369
43c3b79c-db82-4885-8a08-7ea692fb50ce
名前 / ファイル ライセンス アクション
9164_PFR.pdf 9164_PFR (694.3 kB)
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Item type 学術雑誌論文 / Journal Article(1)
公開日 2022-07-08
タイトル
タイトル Potential of Copper Alloys using a Divertor Heat Sink in the Helical Reactor FFHR-d1 and their Brazing Properties with Tungsten Armor by using the Typical Candidate Filler Materials
言語
言語 eng
キーワード
主題Scheme Other
主題 copper alloy
キーワード
主題Scheme Other
主題 tungsten
キーワード
主題Scheme Other
主題 brazing
キーワード
主題Scheme Other
主題 neutron irradiation
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
著者 TOKITANI, Masayuki

× TOKITANI, Masayuki

TOKITANI, Masayuki

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MASUZAKI, Suguru

× MASUZAKI, Suguru

MASUZAKI, Suguru

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HIRAOKA, Yutaka

× HIRAOKA, Yutaka

HIRAOKA, Yutaka

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NOTO, Hiroyuki

× NOTO, Hiroyuki

NOTO, Hiroyuki

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TAMURA, Hitoshi

× TAMURA, Hitoshi

TAMURA, Hitoshi

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TANAKA, Teruya

× TANAKA, Teruya

TANAKA, Teruya

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MUROGA, Takeo

× MUROGA, Takeo

MUROGA, Takeo

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SAGARA, Akio

× SAGARA, Akio

SAGARA, Akio

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FFHR Design Group

× FFHR Design Group

FFHR Design Group

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著者ID
内容記述タイプ Other
内容記述 0000-0002-3744-2481
抄録
内容記述タイプ Abstract
内容記述 A tungsten block is supposed to be used as a divertor armor material on the helical reactor FFHR-d1. On the other hand, material selection of the heat sink and bonding technique between armor and heat sink are currently under investigation. On the material selection, copper alloy has a large advantage for the thermal conductivity, but its material properties such as toughness and thermal conductivity, are dramatically decreased due to the neutron irradiation. However, from the assessment of the neutronics environment on the divertor region of the FFHR-d1, copper alloys could be used for a heat sink especially at the outer divertor. In the ITER case, copper alloy (CuCrZr) pipes are joined by a brazing technique with Nicuman37 filler material. This combination has not been optimized for the FFHR-d1, because the toughness of the CuCrZr at high temperature over 450 °C is dramatically decreased with increasing the temperature. As such, another candidate is an oxide dispersion-strengthened copper alloy (ODS-Cu) such as GlidCop®. For the bonding technique, a reliable brazing combination between “two kinds of copper alloys” and “three kinds of filler materials (MBF-20, BNi-6, Nicuman37)” were investigated from a viewpoint of mechanical strength. The most superior fracture strength among the three filler materials was BNi-6 with GlidCop®.
書誌情報 Plasma and Fusion Research

巻 10, 号 Special Issue 2, p. 3405035, 発行日 2015-04-16
書誌的事項
the 24th International Toki Conference on Expanding Horizons of Plasma and Fusion Science through Cross-Fertilization
出版者
出版者 The Japan Society of Plasma Science and Nuclear Fusion Research
ISSN
収録物識別子タイプ ISSN
収録物識別子 1880-6821
書誌レコードID
収録物識別子タイプ NCID
収録物識別子 AA12346675
DOI
関連タイプ isIdenticalTo
識別子タイプ DOI
関連識別子 10.1585/pfr.10.3405035
権利
権利情報 (c) 2015 The Japan Society of Plasma Science and Nuclear Fusion Research
関連サイト
識別子タイプ DOI
関連識別子 https://doi.org/10.1585/pfr.10.3405035
関連名称 Publisher version
著者版フラグ
出版タイプ VoR
出版タイプResource http://purl.org/coar/version/c_970fb48d4fbd8a85
NAIS
9164
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