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Prediction of ICRF minority heating schemes for JET D–T experiments

D Gallart, M J Mantsinen, J Manyer, E Planas, D M A Taylor, J Garcia, D Frigione, L Garzotti, Hyun-Tae Kim, M Nocente2022年Plasma Physics and Controlled FusionIF 2.2出版社

Achieving high-performance conditions and maximizing the fusion yield of plasma discharges have been one of the main goals of recent Joint European Torus (JET) campaigns in preparation for its second deuterium–tritium (D–T) campaign. The simulations shown in this work delve into the role of external heating using neutral beam injection (NBI) and radio-frequency waves in the ion cyclotron range of frequencies (ICRF) in order to optimise high fusion performance in the JET tokamak. A baseline discharge with record neutron rate is used as a reference in order to perform a D–T prediction, which considers the NBI+RF synergy. In this work, our focus is on JET's two main minority schemes, H and 3He. This study tackles the heating mechanisms by which these schemes reach high-performance conditions. The H scheme typically boosts the ICRF fusion enhancement through the second D harmonic heating, whereas 3He minority is characterised by its strong bulk ion heating. Both features are beneficial for increasing the fusion yield. Nevertheless, the minority concentration is a relevant parameter, which needs to be assessed to understand in which concentration ranges the benefits of each particular minority scheme are met. Therefore, the main objective of this work is to assess in which concentration range the ICRF fusion enhancement and bulk ion heating are optimal, for H and 3He, respectively. Under these conditions, our prediction suggests 3He concentration should stay above 1.2% and H should remain below 2.2%.

日本語訳

JET(共同欧州トーラス)の第2次重水素-三重水素(D-T)キャンペーンに向けた最近の取り組みにおいて、高性能条件の達成と核融合出力の最大化は、主要な目標の一つである。本稿で示すシミュレーションは、JETトーラスにおける高核融合性能の最適化を目的として、中性粒子ビーム入射(NBI)およびイオンサイクロトロン周波数帯(ICRF)における高周波を用いた外部加熱の役割を詳しく調べるものである。記録的な中性子出力を達成した基準放電を参照として、NBIとICRFの相乗効果を考慮したD-T予測を行う。本研究では、JETの2つの主要な少数種加熱スキーム、すなわち水素(H)およびヘリウム3(3He)に焦点を当てる。これらのスキームが高性能条件に到達する加熱メカニズムを考察する。Hスキームは、第2高調波重水素加熱を通じてICRFによる核融合増強を典型的にもたらす一方、3He少数種加熱は、バルクイオン加熱の強化を特徴とする。両者は核融合収率の向上に寄与する。しかしながら、少数種濃度は重要なパラメータであり、各少数種スキームの利点が発揮される濃度範囲を評価する必要がある。そこで、本研究の主目的は、Hおよび3Heそれぞれについて、ICRF核融合増強とバルクイオン加熱が最適となる濃度範囲を評価することである。これらの条件下での予測によれば、3He濃度は1.2%以上、H濃度は2.2%未満に維持されるべきであることが示唆される。

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