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A small tokamak conceptual design for volumetric neutron source

L.J Qiu, Y Wu, Y.C Wu, G.S Luan, Y.W Yang1995年Fusion Engineering and DesignIF 1.7出版社

AbstractThe small tokamak conceptual design based on the fusion-fission hybrid reactor has been studied for a long time for breeding fuel and transmutation of high level waste. If poloidal distributions of neutron wall loading and flux are considered, the midplane equatorial port can be used to test some components, such as blanket modules at a neutron wall loading of 1 MW m−2 in a volume of 1.3 m × 1.3 m × 0.8 m, which can satisfy preliminary requirements for testing some components in fusion environment.

日本語訳

核融合-核分裂ハイブリッド炉に基づく小型トカマクの概念設計は、燃料増殖と高レベル廃棄物の核変換を目的として長期間研究されてきた。中性子壁負荷とフラックスのポロイダル分布を考慮すると、赤道面ポートは、1.3 m × 1.3 m × 0.8 mの体積において1 MW m−2の中性子壁負荷でブランケットモジュールなどの一部の構成要素を試験するために使用でき、これは核融合環境における一部の構成要素の試験に関する予備的要件を満たすことができる。

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