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Ignitor neutronics and activation

P. Batistoni, P. Corsaro, S. Rollet, M. Zucchetti1996年Fusion Engineering and DesignIF 1.7出版社

AbstractThe neutron and gamma fluxes in all the main components of the projected Ignitor tokamak are calculated and discussed. The results are obtained using the 3-D Monte Carlo code mcnp with a detailed description of the device geometry and an accurate representation of the neutron source. The neutron-induced radioactivity, contact dose rates, and radiation damage of the relevant parts of the device are then derived. The consequences on the life and maintenance of device components, the exposure of personnel working in tokamak environments, and the disposal of components after shutdown are described.

日本語訳

計画されたIgnitorトカマクの主要構成要素すべてにおける中性子およびガンマ線フラックスを計算し、考察する。これらの結果は、装置の詳細な記述と中性子源の正確な表現を備えた3次元モンテカルロコードMCNPを用いて得られたものである。関連する各部分における中性子誘起放射能、接触線量率、および放射線損傷を導出する。さらに、装置構成要素の寿命と保守、トカマク環境で作業する人員の被曝、ならびに運転停止後の構成要素の廃棄に関わる影響について述べる。

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