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Design study of nuclear shielding and fuel cycle for steady-state tokamak device JT-60SU

Naoyuki Miya, Takumi Hayashi, Yutaka Suzuki, Keisuke Nagashima, Masayuki Nagami1997年Fusion Engineering and DesignIF 1.7出版社

AbstractConceptual design studies of nuclear shielding and fuel cycle based on nuclear safety aspects are presented for the steady-state tokamak device JT-60 Super Upgrade (JT-60SU). Combination of tungsten and SS-316 materials is newly proposed for the candidate vessel material in addition to the titanium alloy which is chosen as the low activation material so far in JT-60SU. This proposal also meets the design requirements of the nuclear shielding for a D-D neutron production rate of 1×1018 s−1. The fuel cycle and tritium recovery system are designed for steady-state operation with the annual tritium production of 0.2 g and gas flow rate of 20 Pa m3 s−1, most of which is deuterium gas. Concepts of a multiple-barrier tritium containment system and room isolation system are employed for safe tritium processing in the system, which can prevent leakage and propagation to the environment in the case of accidental tritium release.

日本語訳

抄録 定常運転トカマク装置JT-60スーパーアップグレード(JT-60SU)について、核遮蔽および核燃料サイクルの概念設計を核安全の観点から示す。タングステンとSS-316の組合せが、これまでJT-60SUにおいて低放射化材料として選定されてきたチタンに加えて、新たに容器材料の候補として提案される。この提案は、1×10¹⁸ s⁻¹のD-D中性子生成率に対する核遮蔽の設計要件も満たす。燃料サイクルおよびトリチウム回収システムは、年間トリチウム生成量0.2g、ガス流量20 Pa m³ s⁻¹(その大部分は重水素ガス)の定常運転向けに設計される。多重バリアトリチウム閉じ込めシステムおよび室閉じ込めシステムの概念が、システム内での安全なトリチウム処理のために採用され、これにより事故時のトリチウム放出が環境への漏洩および拡散を防止できる。

装置

jt-60sa中精度(概要文一致)

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Steady stateShielding
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