An effective disruption mitigation system in a tokamak reactor should limit the exposure of the wall to localized heat losses and to the impact of high current runaway electron beams, and avoid excessive forces on the structure. We evaluate with respect to these aspects a two-stage deuterium-neon shattered pellet injection in an ITER-like plasma, using simulations with the DREAM framework [M. Hoppe et al (2021) Comp. Phys. Commun. 268, 108098]. To minimize the obtained runaway currents an optimal range of injected deuterium quantities is found. This range is sensitive to the opacity of the plasma to Lyman radiation, which affects the ionization degree of deuterium, and thus avalanche runaway generation. The two-stage injection scheme, where dilution cooling is produced by deuterium before a radiative thermal quench caused by neon, reduces both the hot-tail seed and the localized transported heat load on the wall. However, during nuclear operation, additional runaway seed sources from the activated wall and tritium make it difficult to reach tolerably low runaway currents.
Quantitative 3D non-linear simulations of shattered pellet injection in ASDEX Upgrade using JOREK
Max Planck Institute for Plasma Physics（马克斯·普朗克等离子体物理研究所）；Beihang University（北京航空航天大学）；ITER Organization（国际热核聚变实验堆组织）；Institute of Plasma Physics of the CAS（捷克科学院等离子体物理研究所）；CEA/IRFM（法国原子能和替代能源委员会/核聚变研究集成设施）；École Polytechnique Fédérale de Lausanne (EPFL)（洛桑联邦理工学院）
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。
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）
Evolution of SPI-induced disruptions in ASDEX Upgrade
Max Planck Institute for Plasma Physics（马克斯·普朗克等离子体物理研究所）；Institute of Plasma Physics of the CAS（捷克科学院等离子体物理研究所）；Institute for Applied Physics（应用物理研究所）
