For the first time the pellet cycle of a multiple-isotope plasma is successfully reproduced with reduced turbulent transport modelling, within an integrated simulation framework. Future nuclear fusion reactors are likely to be fuelled by cryogenic pellet injection, due to higher penetration and faster response times. Accurate pellet cycle modelling is crucial to assess fuelling efficiency and burn control. In recent JET tokamak experiments, deuterium pellets with reactor-relevant deposition characteristics were injected into a pure hydrogen plasma. Measurements of the isotope ratio profile inferred a Deuterium penetration time comparable to the energy confinement time. The modelling successfully reproduces the plasma thermodynamic profiles and the fast deuterium penetration timescale. The predictions of the reduced turbulence model QuaLiKiz in the presence of a negative density gradient following pellet deposition are compared with GENE linear and nonlinear higher fidelity modelling. The results are encouraging with regard to reactor fuelling capability and burn control.
Integrated full pulse modeling for pellet injection in tokamaks: HPI2 model improvement and validation in WEST
DIFFER – Dutch Institute for Fundamental Energy Research（荷兰基础能源研究所）；Eindhoven University of Technology（埃因霍温理工大学）；ITER Organization（国际热核聚变实验堆组织）；CEA Cadarache, IRFM（法国原子能和替代能源委员会卡达拉舍校区，核聚变研究集成设施）
本文改进了 HPI2 模型，通过自洽的等离子体释放空间步长计算，提高了数值稳定性，并在 WEST 实验中验证了其预测能力，支持其在集成建模中的应用。
Isotope Effects on TEM-driven Turbulence and Zonal Flows in Helical and Tokamak Plasmas
National Institute for Fusion Science, National Institutes of Natural Sciences（国立研究開発法人 国立統合物理学研究所 核融合科学研究所）；The Graduate University for Advanced Studies（総合研究大学院大学）；Faculty of Arts and Sciences, Komazawa University（駒澤大学 文学部・理学部）；Nagoya University（名古屋大学）
Spacecraft heat shield study in the DIII-D tokamak
University of California San Diego（加州大学圣迭戈分校）；Auburn University（奥本大学）；General Atomics（通用原子能公司）；Princeton Plasma Physics Laboratory（普林斯顿等离子体物理实验室）；Baylor University（贝勒大学）；University of Stuttgart（斯图加特大学）；Oak Ridge National Laboratory（橡树岭国家实验室）；Lawrence Livermore National Laboratory（劳伦斯利弗莫尔国家实验室）
Neural network predictions of plasma confinement loss in Wendelstein 7-X pellet-fueled discharges
Princeton Plasma Physics Laboratory（普林斯顿等离子体物理实验室）；Max Planck Institute for Plasma Physics（马克斯·普朗克等离子体物理研究所）；SUNY Cortland（纽约州立大学科特兰分校）；MIT Plasma Science and Fusion Center（麻省理工学院等离子体科学与聚变中心）
Investigation of turbulent transport regimes in the tokamak edge by using two-fluid simulations
本文利用单零组态磁通驱动双流体模拟的结果，研究了托卡马克边缘湍流输运的过程。确定了三种湍流输运机制：（i）一个发展的输运区，其湍流由交换不稳定性驱动，与托卡马克操作的标准L模式具有许多共同特征，（ii）一个抑制的输运区，其特征在于较高的能量约束时间值，由Kelvin-Helmholtz不稳定性驱动的低振幅相对波动，强E x B剪切流，和一个传输障碍的形成，回忆的H-模式，和（iii）退化的约束制度，其特征在于一个灾难性的大的湍流驱动的湍流传输，这提醒了格林沃尔德密度极限的交叉。我们推导出的压力梯度长度的解析表达式在这三个制度。通过增加热源或降低碰撞性获得从发展的输运状态到抑制的输运状态的过渡，反之亦然，对于从发展的输运状态到退化的约束状态的过渡。的功率阈值的解析表达式，以访问抑制的传输制度，连接到H-模式访问的功率阈值，以及在进入退化的约束制度，相关的格林沃尔德密度之前可实现的最大密度，也来自。实验依赖性的H-模式访问的功率阈值密度，托卡马克大半径，和同位素质量的检索。密度极限的解析估计包含了对等离子体电流和托卡马克小半径的正确依赖。
