DocumentCode
2015095
Title
TFTR status and plans
Author
Williams, Michael D.
Author_Institution
Plasma Phys. Lab., Princeton Univ., NJ, USA
fYear
1989
fDate
2-6 Oct 1989
Firstpage
1
Abstract
The Tokamak Fusion Test Reactor (TFTR) has been operating and providing physics data in regimes approaching those required for a fusion power reactor. Much progress has been made in improving the fusion product gain, Q , and TFTR routinely produces plasmas yielding a neutron source strength >1016 neutrons/second from D-D reactions resulting from up to 30 mW of neutral beam injection. TFTR has already produced D-D fusion plasmas which correspond to Q =0.5 if a D-T fuel mixture were substituted and enhancement factors due to higher neutral beam power capability with D0+T0 beams, increased global energy confinement time from favorable mass scaling using tritium, and a modest contribution of alpha-particle heating are taken into account. Recent redirection of the Magnetic Fusion Energy Program has shifted the near-term emphasis on TFTR from preparing for tritium operation and demonstration of energy breakeven to studying plasma fluctuations and transport in order to improve understanding and develop physics-based models of the plasma heat loss mechanisms
Keywords
Tokamak devices; fusion reactor ignition; fusion reactor theory and design; TFTR; Tokamak Fusion Test Reactor; alpha-particle heating; energy breakeven; enhancement factors; fusion power reactor; fusion product gain; global energy confinement time; neutral beam injection; neutron source strength; plasma fluctuations; plasma heat loss mechanisms; Inductors; Magnetic confinement; Neutrons; Particle beams; Physics; Plasma confinement; Plasma sources; Plasma transport processes; Testing; Tokamaks;
fLanguage
English
Publisher
ieee
Conference_Titel
Fusion Engineering, 1989. Proceedings., IEEE Thirteenth Symposium on
Conference_Location
Knoxville, TN
Type
conf
DOI
10.1109/FUSION.1989.102160
Filename
102160
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