EAST实时等离子体平衡重建及控制系统集成研究

The Neoclassical Tearing Mode and Edge Localized Mode are observed in EAST high performance plasma discharges. In order to control these instabilities, a robust control on plasma position, boundary and profile parameters must be achieved, which means the high performance tokamak discharge requests not only the reliable and accurate plasma position and boundary control but also the dynamic control. To achieve the accurate parameters control, such as the safety profile, current profile and pressure profile control, the real-time plasma equilibrium reconstruction, include the internal profile fitting information, should be developed. And the real-time reconstruction system must be integrated into EAST plasma control system to provide accurate, reliable and real-time plasma position, boundary and profile parameters, makes it as a routine server for EAST real-time plasma discharge control. The fast plasma equilibrium reconstruction code PEFIT, running on the GPU, using magnetic diagnostic as the input measurement, provides solid foundation for this project.

EAST托卡马克在高参数等离子体物理放电实验中已经观察到诸如新经典撕裂模和边界局域模等不稳定性现象。这些不稳定性的控制需要对等离子体的位形和剖面参数有良好的控制，所以EAST高参数托卡马克运行必然要求等离子体控制系统在精确的位形控制基础上具有稳定可靠的动理论控制。为了精确控制诸如安全因子剖面、电流剖面和压力剖面等物理参数，必须发展在内部诊断测量支持下的包含内部剖面反演的实时等离子体平衡重建并与等离子体控制系统并建立与EAST等离子体控制系统之间稳定可靠实时的数据交互集成，使实时平衡重建系统成为EAST等离子体控制系统日常放电实验的例行服务。EAST上建立的基于电磁测量数据的GPU架构下的等离子体快速平衡重建代码PEFIT获得了国际同行的高度评价，将为本项目的顺利开展奠定坚实基础。

EAST托卡马克在高参数等离子体物理放电实验中已经观察到诸如新经典撕裂模和边界局域模等不稳定现象。这些不稳定性的控制需要对等离子体的位形和剖面参数有良好的控制，所以EAST高参数托卡马克运行必然要求等离子体控制系统在精确的位形控制基础上具有稳定可靠的动理论控制。为了精确控制诸如安全因子剖面、电流剖面和压力剖面等物理参数，必须发展在内部诊断测量支持下的包含内部剖面反演的实时等离子体平衡重建并与EAST等离子体控制系统之间建立稳定可的实时数据交互集成，使实时平衡重建系统成为EAST等离子体控制系统日常放电实验的例行服务。EAST上建立的基于电磁测量数据的GPU架构下的等离子体快速平衡重建代码PEFIT获得了国际同行的高度评价，将为本项目的顺利开展奠定坚实基础。