Abstract
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[1], in real-time, RTEFIT[2]. 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.
| Original language | English (US) |
|---|---|
| Pages (from-to) | 219-221 |
| Number of pages | 3 |
| Journal | IEEE Transactions on Nuclear Science |
| Volume | 47 |
| Issue number | 2 PART 1 |
| DOIs | |
| State | Published - 2000 |
| Externally published | Yes |
All Science Journal Classification (ASJC) codes
- Nuclear and High Energy Physics
- Nuclear Energy and Engineering
- Electrical and Electronic Engineering