FusionPapers
図版検索トレンドwiki日本の研究
© 2026 FUSIONPAPERS
About法務情報
トップに戻る

Development of advanced Nb3Al superconductors for a fusion demo plant

Norikiyo Koizumi, Takao Takeuchi, Kiyoshi Okuno2005年被引用 39Nuclear FusionIF 3出版社

A Nb3Al superconductor inherently has the outstanding features of a high critical field and an excellent strain tolerance in critical current performance. The Japan Atomic Energy Research Institute developed the world's first large Nb3Al coil using jelly-roll processed Nb3Al strands. This coil was successfully operated up to the nominal current and field of 46 kA and 13 T, respectively. The test results demonstrated that a Nb3Al conductor is suitable for application in high field, large magnets, such as the toroidal field (TF) coils in a fusion reactor. In parallel with this work, a Nb3Al strand having a high critical current at high field has been developed by the National Institute of Materials Science. This strand cannot incorporate enough copper stabilizer, resulting in poor stability, since it is heat-treated at a much higher temperature than the melting temperature of copper. In order to find a solution to this issue, we performed an analytical study, and it showed that the externally incorporated copper after the high temperature heat treatment is effective for stabilization when the electric conductance and heat transfer coefficient between the Nb3Al strand and the external copper are more than 10 MS m−1 and 10 kW m−2 K−1, respectively. Since they seem to be attained by using present conductor technologies, the development of a TF coil operated at a high field around 16 T seems promising.

日本語訳

Nb₃Al超伝導体は、本質的に高い臨界磁場と臨界電流特性における優れたひずみ耐性という優れた特徴を有している。日本原子力研究所は、ジェリーロール法で作製したNb₃Al素線を用いて、世界初の大型Nb₃Alコイルを開発した。このコイルは、定格電流46 kAおよび定格磁場13 Tまでそれぞれ正常に運転された。試験結果は、Nb₃Al導体が、核融合炉のトロイダル磁場(TF)コイルのような高磁場・大型マグネットへの適用に適していることを実証した。この研究と並行して、高磁場で高い臨界電流を有するNb₃Al素線が物質・材料研究機構によって開発された。この素線は、銅の融点よりもはるかに高い温度で熱処理されるため、十分な銅安定材を組み込むことができず、安定性に劣る。この問題の解決策を見出すため、我々は解析的検討を行い、高温熱処理後に外部から組み込む銅が、Nb₃Al素線と外部銅との間の電気伝導度および熱伝達係数がそれぞれ10 MS m⁻¹および10 kW m⁻² K⁻¹以上である場合に、安定化に有効であることを示した。これらは現在の導体技術を用いることで達成可能と思われるため、約16 Tの高磁場で運転されるTFコイルの開発は有望であると思われる。

wiki

DEMO
この論文にはまだAI要約がありません。

関連論文

Development of a 13-T and 40-kA Nb3Al conductor for toroidal coils of fusion reactors

1998Fusion Engineering and Design

Advanced fusion technologies developed for JT-60 superconducting tokamak

2004Nuclear Fusion

Performance test and analysis of the first large-scale cable-in-conduit conductor with high Jc Nb3Sn strand for fusion reactor

2021Nuclear Fusion

Development and test of the poloidal field prototype coil POLO at the Forschungszentrum Karlsruhe

1997Fusion Engineering and Design

Technology development and mass production of Nb3Sn conductors for ITER toroidal field coils in Japan

2011Nuclear Fusion

DC performance and AC loss of sub-size MgB2 CICC conductor for fusion magnet application

2022Nuclear Fusion

Development of advanced superconducting coil technologies for the National Centralized Tokamak

2005Nuclear Fusion

(Nb, Ti)3Sn forced-flow-cooled superconductor

1993Fusion Engineering and Design

Joints for large superconducting conductors

2001Fusion Engineering and Design

Design and development of high-temperature superconducting magnet system with joint-winding for the helical fusion reactor

2015Nuclear Fusion