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Predictive calculation of neutral beam heating plasmas in EAST tokamak by NUBEAM code for certain parameter ranges

机译:通过NUBEAM代码对某些参数范围的EAST托卡马克中性束加热等离子体进行预测计算

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摘要

A predictive calculation is carried out for neutral beam heating of fusion plasmas in EAST by using NUBEAM code under certain plasma conditions. Results calculated are analyzed for different plasma parameters. Relations between major plasma parameters, such as density and temperature, are obtained and key physical processes in the neutral beam heating, including beam power deposition, trapped fraction, heating efficiency, and power loss, are simulated. Other physical processes, such as current-drive, toroidal rotation and neutron emission, are also discussed.
机译:通过在某些等离子体条件下使用NUBEAM代码对EAST中的融合等离子体进行中性束加热进行了预测计算。针对不同的血浆参数分析计算的结果。获得了主要等离子体参数(例如密度和温度)之间的关系,并模拟了中性束加热中的关键物理过程,包括束功率沉积,捕获分数,加热效率和功率损耗。还讨论了其他物理过程,例如电流驱动,环形旋转和中子发射。

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