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Neutronic and photonic analysis of the single box water-cooled lithium lead blanket for a DEMO reactor

G Vella, L Giancarli, E Oliveri, G Aiello1998年Fusion Engineering and DesignIF 1.7出版社

AbstractThe water-cooled Pb–17Li demonstration plant (DEMO) breeding blanket line was selected in 1995 as one of the two EU lines to be further developed in the next decade. In this paper the results of a neutronic and photonic analysis of the `single box' concept is presented. A full three-dimensional model, including the whole assembly and many of the DEMO reactor components, has been developed, together with a three-dimensional neutron source. A tritium breeding ratio (TBR) value of 1.16, with no ports and a Li6 enrichment of 90%, has been obtained and a further analysis has been performed to determine Li6 enrichment that would still ensure tritium breeding self-sufficiency. Selected power densities, calculated for the different materials and zones, are also presented. Material damage through displacements per atom and helium gas production has been investigated. Some shielding capability considerations are presented too.

日本語訳

水冷Pb–17Li実証プラント(DEMO)増殖ブランケット系統は、1995年に今後10年間でさらに開発を進めるEUの2系統のうちの1つとして選定された。本論文では、「シングルボックス」概念の中性子解析および光子解析の結果を提示する。アセンブリ全体とDEMO炉の多くの構成要素を含む完全な3次元モデルが、3次元中性子源とともに構築された。ポートなし、Li6濃縮度90%の場合、トリチウム増殖比(TBR)値1.16が得られ、さらにトリチウム増殖自給自足を確保できるLi6濃縮度を決定するための追加解析が実施された。異なる材料および領域について計算された選択された出力密度も提示する。原子当たりの変位およびヘリウム生成による材料損傷も示す。いくつかの遮蔽性能に関する考察も提示する。

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DEMOLithiumLead-lithium eutectic
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