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Using the shield for thermal energy storage in pulsar

G.T. Sager, D.-K. Sze, C.P.C. Wong, C.G. Bathke, L. Waganer1995年Fusion Engineering and DesignIF 1.7出版社

AbstractThe PULSAR pulsed tokamak power plant design utilizes the outboard shield for thermal energy storage to maintain full 1000 MW(e) output during the dwell period of 200 s. Thermal energy resulting from direct nuclear heating is accumulated in the shield during the 7200 s fusion power production phase. The maximum shield temperature may be much higher than that for the blanket because radiation damage is significantly reduced. During the dwell period, thermal power discharged from the shield and coolant temperature are simultaneously regulated by controlling the coolant mass flow rate at the shield inlet. This is facilitated by throttled coolant bypass. Design concepts using helium and lithium coolant have been developed. Two-dimensional time-dependent thermal hydraulic calculations were performed to confirm performance capabilities required of the design concepts. The results indicate that the system design and performance can accommodate uncertainties in material limits or the length of the dwell period.

日本語訳

パルス運転トカマク発電所設計は、200秒の待機期間中に1000 MW(e)の全出力を維持するために、熱エネルギー貯蔵に外側遮蔽体を利用する。直接核加熱による熱エネルギーは、7200秒の核融合出力生成期間中に遮蔽体内に蓄積される。放射線損傷が大幅に低減されるため、遮蔽体の最高温度はブランケットのそれよりもはるかに高くなる可能性がある。待機期間中、遮蔽体から放出される熱出力と冷却材温度は、遮蔽体入口における冷却材質量流量を制御することによって同時に調整される。これは、絞り付きバイパスによって実現される。ヘリウム冷却材とリチウム冷却材を用いた設計概念が開発されている。設計概念に要求される性能を確認するために、二次元時間依存熱流動計算が実施された。計算結果は、システム設計と性能が材料不確実性または待機期間の長さに対応できることを示している。

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