TFTR results and plans

Conference · Wed Mar 01 04:00:00 EST 1989 · Fusion Technol.; (United States)

OSTI ID:6216780

Sinnis, J C

The TFTR facility has recently undergone modifications that increase the auxiliary heating capability by the addition of 9 MW of ion cyclotron frequency heating power. In addition, one of the neutral injection beam lines has been reoriented to provide balanced injection capability at full power (27 MW). Results from experiments with this new capability are presented. The TFTR program calls for the initiation of D-T breakeven experiments in the 1990-1991 time frame; additional shielding, tritium neutral beams and reliability upgrades are all prerequisites for the D-T experiments. The planning for this D-T preparation program is discussed.

• Research Organization: Princeton Univ., Princeton Plasma Physics Lab., Princeton, NJ (US)
• OSTI ID: 6216780
• Report Number(s): CONF-881031-
• Conference Information: Journal Name: Fusion Technol.; (United States) Journal Volume: 15:2
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
700101 -- Fusion Energy-- Plasma Research-- Confinement
Heating
& Production
700201 -- Fusion Power Plant Technology-- Blanket Engineering
700203* -- Fusion Power Plant Technology-- Power Supplies
Energy Storage
700205 -- Fusion Power Plant Technology-- Fuel
Heating
& Injection Systems
BEAM INJECTION
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
DATA
DEUTERIUM
EXPERIMENTAL DATA
HEATING
HIGH-FREQUENCY HEATING
HYDROGEN ISOTOPES
ICR HEATING
INFORMATION
ISOTOPES
LIGHT NUCLEI
MODIFICATIONS
NEUTRAL ATOM BEAM INJECTION
NUCLEI
NUMERICAL DATA
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
PERFORMANCE
PLANNING
PLASMA
PLASMA HEATING
RADIOISOTOPES
RELIABILITY
SHIELDING
STABLE ISOTOPES
TFTR TOKAMAK
THERMONUCLEAR REACTORS
TOKAMAK TYPE REACTORS
TRITIUM
YEARS LIVING RADIOISOTOPES