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

Fusion Reactor Design-III (Report on the 3rd IAEA Technical Committee Meeting and Workshop, Tokyo, 1981)

Y. Iso, W.M. Stacey Jr., G.L. Kulcinski, R.A. Krakowski, G.A. Carlson, C. Yamanaka, G. Casini, N. Igata1982年被引用 13Nuclear FusionIF 3出版社

A brief summary is given of the plenary sessions of the 3rd IAEA Technical Committee Meeting and Workshop on Fusion Reactor Design and Technology. The large tokamak experiments now under construction have brought fusion research to the threshold of fusion reactor power. A number of major in-depth reactor design studies are reported such as the 650-MW INTOR near term experimental fusion reactor based upon essentially current technology. Also reported are studies of commercial reactor designs. Results are given of the discussions of seven workshops that were based on the papers presented. These groups evaluated the current status and identified key problem areas for each in the following areas: near-term tokamaks, long-term tokamaks, toroidal systems (alternative concepts), open systems, inertial confinement, systems (advanced fuels, hybrids, etc.), and fusion reactor materials. The importance of beginning now to prepare for the next major step in fusion reactor development was emphasized and the benefits of international co-operation were evident in the consensus reached in the INTOR results and the strong influence it has had on the direction of the leading national design efforts.

日本語訳

第3回IAEA核融合炉設計と技術に関する技術委員会会合およびワークショップの本会議の簡単な要約が示される。現在建設中の大型トカマク実験装置は、核融合研究を核融合炉出力の閾値にまで到達させた。基本的に現在の技術に基づく650-MW INTOR短期的実験核融合炉など、いくつかの主要な詳細な炉設計研究が報告されている。商業炉設計の研究も報告されている。提示された論文に基づく7つのワークショップの議論の結果が示される。これらのグループは、以下の分野のそれぞれについて現在の状況を評価し、主要な問題領域を特定した: 短期的トカマク、長期的トカマク、トロイダルシステム(代替概念)、開放系、慣性閉じ込め、システム(先進燃料、ハイブリッドなど)、および核融合炉材料。核融合炉開発における次の主要なステップに備えるために今から始めることの重要性が強調され、INTORの結果で達成された合意と、その合意が主要な国内設計努力の方向に与えた強い影響において、国際協力の利点が明らかであった。

この論文にはまだAI要約がありません。

関連論文

Fusion Reactor Design-II (Report on the Second IAEA Technical Committee Meeting and Workshop, Madison, 1977)

1978Nuclear Fusion

Overview of the Japanese fusion reactor studies programme

2000Fusion Engineering and Design

Design study of fusion experimental reactor at JAERI

1989Fusion Engineering and Design

Fusion reactor design and technology 1986

1988Fusion Engineering and Design

ITER: the first experimental fusion reactor

1995Fusion Engineering and Design

Synchronized fusion development considering physics, materials and heat transfer

2017Nuclear Fusion

Effect of particle pinch on the fusion performance and profile features of an international thermonuclear experimental reactor-like fusion reactor

2015Physics of Plasmas

Status and prospects of the European Fusion programme

1991Fusion Engineering and Design

International Tokamak Reactor – Phase I (Executive Summary of the IAEA Workshop, 1981)

1982Nuclear Fusion

Remote handling technology development for fusion experimental reactors

1995Fusion Engineering and Design