Upgrade for the National Spherical Torus Experiment control computer

被引：0

作者：

Mueller, D. ^{[1
]}

Gates, D.A. ^{[1
]}

Ferron, J.R. ^{[1
]}

机构：

[1] Princeton Plasma Physics Lab, Princeton, United States

来源：

IEEE Transactions on Nuclear Science | 2000年 / 47卷 / 2 I期

关键词：

Algorithms - Computer control systems - Control system analysis - Current density - Eddy currents - Fusion reactions - Least squares approximations - Magnetoplasma - Plasma confinement - Plasma diagnostics - Program processors - Real time systems;

D O I：

暂无

中图分类号：

学科分类号：

摘要：

The National Spherical Torus Experiment (NSTX) is a proof of scientific principle experiment as a magnetic fusion containment device. A primary goal of NSTX operations is control of the plasma current, position and shape in real time for a wide range of plasma pressure and current density profiles. In order to employ the best calculation of the plasma current, position and shape, it is planned to implement the equilibrium analysis code, EFIT, in real-time, RTEFIT. EFIT inverts the Grad-Shafranov equation and performs a least squares fit to the magnetics data. EFIT and RTEFIT are also capable of providing the plasma current profile and the plasma pressure profile from analysis of diagnostic data. The calculation time for RTEFIT using the present NSTX control computer system is comparable to the expected energy confinement time on NSTX and is thus slower than desired. A computer upgrade based upon the new G4 (MPC7400) processors will permit the RTEFIT calculation loop to complete in about 2 ms. The presence of the passive plates further complicates the control algorithm to be used in conjunction with RTEFIT. The planned approach is to measure the eddy currents in the passive plates and to use the transient response of the coils to minimize the total shell current effect.

引用

页码：219 / 221