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

Design study of a tritium transport package for future fusion reactors

S. O’hira, T. Suzuki, S. Hode, M. Nishi1999年Fusion Engineering and DesignIF 1.7出版社

AbstractThe first design of a tritium transport package with large capacity and compact size, which can be applicable to tritium transport for International Thermonuclear Experimental Reactor (ITER) was developed. To verify that the package complies with the requirements for the BU type package stipulated in the IAEA regulation of transport packages, structural and thermal analysis were made for hypothetical accident conditions during transport. Structural analysis with the volumetric displacement method (VDM) method under conditions of 9 m drop test and thermal analysis with the ABAQUS code under conditions of 800°C×30 min thermal test showed that the package complied with the requirements for BU type transfer packages. An additional safety analysis was to confirm integrity of the confinement components when the package sinks in the deep sea of 6000 m in depth.

日本語訳

国際熱核融合実験炉(ITER)へのトリチウム輸送に適用可能な、大型かつコンパクトなトリチウム輸送容器の最初の設計を開発した。輸送容器に関するIAEA規則で定められたBU型容器の要件を満たすことを検証するため、輸送中の仮想事故条件下での構造解析及び熱解析を実施した。構造解析は体積変位法(VDM)を用いて9m落下条件下で行い、熱解析はABAQUSコードを用いて800℃×30分の熱条件下で行い、その結果、容器がBU型輸送容器の要件を満たすことを確認した。さらに、深度6000mの深海に容器が沈没した場合の閉じ込め構成要素の健全性を確認するための追加安全解析を実施した。

装置

iter中精度(概要文一致)

wiki

TritiumTritium transport
この論文にはまだAI要約がありません。

関連論文

Development of ITER tritium transport package

2013Fusion Engineering and Design

Fusion nuclear systems design and analysis

1988Fusion Engineering and Design

Preliminary engineering analysis for CN HCCB TBM regarding ITER new baseline scenario

2026Nuclear Fusion

Environmental aspects of tritium and active waste—A comparison of four inertial confinement fusion reactor concepts

1996Fusion Engineering and Design

Multi-functional code for hydrogen isotopes transport analyses: verification & validation against fusion-relevant applications

2025Nuclear Fusion

Tritium management in ITER test blanket systems port cell for maintenance operations

2024Nuclear Fusion

Comparisons of facility-specific and generic component failure rates for tritium-bearing components used in fusion research

2001Fusion Engineering and Design

Tritium transport calculations for the IFMIF Tritium Release Test Module

2014Fusion Engineering and Design

Tritium transport experiments on the JET tokamak

2004Plasma Physics and Controlled Fusion

A novel method for trace tritium transport studies

2009Nuclear Fusion