Digital Coil protection system for the National Spherical Torus experiment upgrade

Author

Hatcher, Ronald E. ; Dong, Junchen ; Erickson, Kristopher ; Mozulay, R. ; Titus, P. ; Zhao, Xingang ; Davis, Wyatt ; DePasquale, S. ; Gerhardt, S. ; Neumeyer, C. ; Sichta, P. ; Tchilinguirian, G. ; Zimmer, G.

Author_Institution

Princeton Plasma Phys. Lab., Princeton, NJ, USA

fYear

2013

Firstpage

1

Lastpage

5

Abstract

An upgrade to the National Spherical Torus Experiment (NSTX) is currently in progress. The NSTX Center Stack Upgrade (NSTX-U) experimental device has an operating space that is both larger and more complex than that of the original NSTX. The mechanical integrity of some machine components can be compromised both by the instantaneous values of combinations of magnet currents and as a result of the time histories thereof. An upgrade to the existing protection systems and methodology is required to allow for both safe and effective use of the expanded operating space. A Digital Coil Protection System (DCPS) is planned as a major component of an upgraded Coil Protection System (CPS).

Keywords

Tokamak devices; fusion reactor safety; plasma toroidal confinement; National Spherical Torus Experiment upgrade; digital coil protection system; expanded operating space safety; machine component mechanical integrity; magnet currents; Algorithm design and analysis; Coils; Computers; Hardware; Physics; Software; Software algorithms; NSTX; coil; magnet; protection; torus;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on

Conference_Location

San Francisco, CA

Print_ISBN

978-1-4799-0169-2

Type

conf

DOI

10.1109/SOFE.2013.6635488

Filename

6635488