Field-reversed configuration formation, translation, and confinement studies on the FRX-C/T experiment

Conference · Tue Jan 01 00:00:00 EST 1985

OSTI ID:5539311

Siemon, R E; Armstrong, W T; Chrien, R E; Hugrass, W N; McKenna, K F; Rej, D J; Tuszewski, M

The field-reversed configuration (FRC) is a high ..beta.. (>50%), prolate compact toroid plasma contained primarily by poloidal magnetic fields. FRC plasmas with parameters, anti n = (1-5)x10/sup 15/cm/sup -3/, T/sub i/ = 0.1-0.8 keV, T/sub e/ = 0.1-0.2 keV, R approx. = 7 cm, B = 5-8 kG, lifetimes less than or equal to300 ..mu..s, are studied on the FRX-C/T experiment at Los Alamos. FRX-C/T consists of a 0.5-m-dia, 1.0-m-long field-reversed theta-pinch coil, and a 0.4-m-dia, 5-m-long translation region into which FRC's are launched, translated, and trapped. A 5-20 mtorr pressure D/sub 2/ fill is introduced into the device by either a gas puff (localized in the theta-pinch source) or static fill system.

• Research Organization: Los Alamos National Laboratory (LANL), Los Alamos, NM (United States)
• DOE Contract Number: W-7405-ENG-36
• OSTI ID: 5539311
• Report Number(s): LA-UR-85-2174; CONF-850927-2; ON: DE85014095
• Resource Relation: Conference: 12. European conference on controlled fusion and plasma physics, Budapest, Hungary, 2 Sep 1985
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
REVERSE-FIELD PINCH
MAGNETIC FLUX
DEUTERIUM
MAGNETIC FIELD CONFIGURATIONS
PLASMA CONFINEMENT
THETA PINCH
CONFINEMENT
HYDROGEN ISOTOPES
ISOTOPES
LIGHT NUCLEI
NUCLEI
ODD-ODD NUCLEI
PINCH EFFECT
STABLE ISOTOPES
700202* - Fusion Power Plant Technology- Magnet Coils & Fields