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Robust control of the safety factor profile and stored energy evolutions in high performance burning plasma scenarios in the ITER tokamak

机译:在ITER托卡马克高性能燃烧等离子体场景中对安全系数分布图和存储的能量演化进行鲁棒控制

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The next step towards the development of a nuclear fusion tokamak power plant is the ITER project. Integrated closed-loop control of the plasma stored energy and safety factor profile (q-profile) is key to maintaining the plasma in a stable state and maximizing its performance. The q-profile evolution in tokamaks is related to the poloidal magnetic flux profile evolution, which is described by a physics model called the magnetic diffusion equation. A first-principles-driven (FPD), nonlinear, control-oriented model of the poloidal magnetic flux profile evolution is obtained by first combining the magnetic diffusion equation with simplified physics-based models of the noninductive current-drives. Secondly, the electron density, electron temperature, and plasma resistivity profiles are modeled as uncertain parameters by defining ranges in which they are expected to be in typical ITER high performance scenarios. This FPD model is then employed to synthesize an H feedback algorithm that utilizes ITER's auxiliary heating/current-drive sources and the total plasma current as actuators to control the q-profile and stored energy in high performance burning plasma scenarios while ensuring the closed-loop system is robust to the uncertainties in the plasma parameters. Finally, the effectiveness of the controller is demonstrated through simulation.
机译:发展核聚变托卡马克发电厂的下一步是国际热核实验堆项目。等离子体存储能量和安全系数曲线(q曲线)的集成闭环控制对于保持等离子体处于稳定状态并最大化其性能至关重要。托卡马克中的q剖面演变与极向磁通剖面演变有关,这由称为磁扩散方程的物理模型来描述。通过将磁扩散方程与非感应电流驱动的简化的基于物理的简化模型相结合,获得了第一性原理驱动(FPD),非线性,面向控制的极向磁通量分布演化模型。其次,通过定义在典型的ITER高性能场景中期望的范围,将电子密度,电子温度和等离子体电阻率曲线建模为不确定参数。然后,该FPD模型用于合成H 反馈算法,该算法利用ITER的辅助加热/电流驱动源和总等离子体电流作为促动器来控制q曲线和高性能燃烧中的存储能量等离子场景,同时确保闭环系统对等离子参数的不确定性具有鲁棒性。最后,通过仿真验证了控制器的有效性。

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