FED-A, an advanced performance FED based on low safety factor and current drive

Technical Report · Mon Aug 01 00:00:00 EDT 1983

DOI:https://doi.org/10.2172/6028937· OSTI ID:6028937

Peng, Y K.M.; Rutherford, P H

The FED-A study aims to quantify the potential improvement in cost-effectiveness of the Fusion Engineering Device (FED) by assuming low safety factor q (less than 2 as opposed to about 3) at the plasma edge and noninductive current drive (as opposed to only inductive current drive). The FED-A performance objectives are set to be : (1) ignition assuming International Tokamak Reactor (INTOR) plamsa confinement scaling, but still achieving a fusion power amplification Q greater than or equal to 5 when the confinement is degraded by a factor of 2; (2) neutron wall loading of about 1 MW/m/sup 2/, with 0.5 MW/m/sup 2/ as a conservative lower bound; and (3) more clearly power-reactor-like operations, such as steady state.

• Research Organization: Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
• DOE Contract Number: W-7405-ENG-26
• OSTI ID: 6028937
• Report Number(s): ORNL/FEDC-83/1; ON: DE83015072
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
FIRST WALL
DESIGN
TOKAMAK TYPE REACTORS
COST
CURRENT-DRIVE HEATING
HIGH-BETA PLASMA
MAGNET COILS
PLASMA MACROINSTABILITIES
Q-VALUE
STABILIZATION
ELECTRIC COILS
ELECTRIC HEATING
ELECTRICAL EQUIPMENT
ENERGY
EQUIPMENT
HEATING
INSTABILITY
JOULE HEATING
PLASMA
PLASMA HEATING
PLASMA INSTABILITY
RESISTANCE HEATING
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
700200* - Fusion Energy- Fusion Power Plant Technology