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Experiments on the Frascati Tokamak Upgrade with a liquid tin limiter

G. Mazzitelli, M.L. Apicella, M. Iafrati, G. Apruzzese, F. Bombarda, F. Crescenzi, L. Gabellieri, A. Mancini, M. Marinucci, A. Romano2019年被引用 19Nuclear FusionIF 3出版社

A capillary porous liquid tin limiter (TLL) was exposed as a plasma-facing component (PFC) in the Frascati Tokamak Upgrade. The TLL was progressively inserted deeper into the scrape-off-layer, very close to the last closed magnetic surface (<0.5 cm). Spectroscopic measurements, a fast IR camera, and Langmuir probes monitored the evolution of tin emission, tin surface temperature, and heat loads on the limiter. The surface temperature rose up to 1700 °C in the hottest limiter region, a value for which tin evaporation is very high. Heat loads in excess of 18 MW m−2 were withstood by the TLL. Numerical simulations performed with the ANSYS code were in agreement with the experimental data, taking into account the heat load deposition profile on the TLL. As long as the surface temperature of the tin limiter is below 1300 °C, the main tin production mechanism is sputtering and the presence of such impurity in the discharge is negligible. When evaporation becomes dominant beyond 1300 °C, tin is the main impurity present in the plasma. Nevertheless, the concentration of tin is on the order of 5  ×  10−4 of the electronic density, and no degradation in plasma performance has been observed. These results are an important experimental confirmation of the possibility to use liquid metals as a PFC solution to the power exhaust for a fusion power plant.

日本語訳

毛細管多孔質液体スズリミッター(TLL)をプラズマ対向部品(PFC)としてフラスカティ・トカマク・アップグレードに曝露した。TLLをスクレイプオフ層内へ徐々に挿入し、最外殻磁気面に非常に近い位置(<0.5 cm)まで到達させた。分光測定、高速IRカメラ、ラングミュアプローブにより、スズの発光、表面温度、リミッターへの熱負荷の時間変化を監視した。リミッターの最も高温となる領域で表面温度は1700 °Cまで上昇し、この値ではスズの蒸発が非常に大きくなる。TLLは18 MW m⁻²を超える熱負荷に耐えた。ANSYSコードによる数値シミュレーションは、TLL上の熱負荷分布を考慮した実験データと一致した。スズリミッターの表面温度が1300 °C未満である限り、主なスズ生成機構はスパッタリングであり、放電中におけるこのような不純物の存在は無視できる程度である。蒸発が1300 °Cを超えて支配的になると、スズがプラズマ中の主な不純物となる。それでも、スズの濃度は電子密度の約5×10⁻⁴のオーダーであり、プラズマ性能の劣化は観測されなかった。これらの結果は、核融合発電炉における排熱問題の解決策として液体金属をPFCとして使用することの可能性を実験的に確認する重要なものである。

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