Improvement of RFX performances by field and impurity control

Author

Buffa, A. ; Gnesotto, F.

Author_Institution

Padova Univ., Italy

Volume

2

fYear

1995

fDate

30 Sep-5 Oct 1995

Firstpage

1395

Abstract

The Reverse Field Pinch experiment RFX has been operated since 1992 with the principal objective of extending the knowledge of RFP confinement to larger dimensions and higher plasma currents. Experiments have been run between 500 and 900 kA; confinement parameters are mainly determined by magnetic field quality and plasma density behaviour. Significant improvements were obtained by feedback controlling the poloidal field configuration and by reducing the impurities produced by plasma-wall interactions

Keywords

fusion reactor theory; fusion reactors; magnetic variables control; plasma impurities; position control; reversed field pinch; 500 to 900 kA; RFX performances; confinement parameters; feedback control; impurity control; magnetic field quality; plasma density behaviour; plasma-wall interactions; poloidal field configuration; reverse field pinch experiment; Calendars; Impurities; Magnetic confinement; Magnetohydrodynamics; Plasma confinement; Plasma density; Plasma diagnostics; Plasma properties; Shape control; Toroidal magnetic fields;

fLanguage

English

Publisher

ieee

Conference_Titel

Fusion Engineering, 1995. SOFE '95. Seeking a New Energy Era., 16th IEEE/NPSS Symposium

Conference_Location

Champaign, IL

Print_ISBN

0-7803-2969-4

Type

conf

DOI

10.1109/FUSION.1995.534487

Filename

534487