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Accession Number DE2013-1022659
Title Overview of the Initial NSTX Experimental Results.
Publication Date 2012
Media Count 12p
Personal Author D. Darrow D. Gates E. Fredrickson L. Grisham M. Bell M. Bitter M. Ono R. E. Bell T. Bigelow W. Blanchard
Abstract A broad range of encouraging advances have been made in the exploration of the Spherical Torus (ST), a very low aspect-ratio tokamak concept. These advances include promising experimental data from pioneering experiments, theoretical predictions, near-term fusion energy development projections such as the Volume Neutron Source, and future applications to power plants. The National Spherical Torus Experiment (NSTX) is a U.S. national research facility located at the Princeton Plasma Physics Laboratory (PPPL). Its focus is on ST related research with an emphasis on finding a cost-effective route to an attractive fusion power plant. NSTX's main mission is to extend the understanding of toroidal plasma physics to new regimes at the mega-ampere level at high plasma beta. The key physics objective of NSTX is to attain an advanced ST regime; i.e., simultaneous ultra high beta (b), high confinement, and high bootstrap current fraction (fbs). This regime is considered essential for the development of an economical power plant because it minimizes the recirculating power and power plant core size. Other NSTX mission elements crucial for ST power plant development are the demonstration of fully non-inductive operation and the development of acceptable power and particle handling concepts.
Keywords Design
Electric currents
Electrons
Elongation
Harmonics
Heating
Helicity
Ion sources
NSTX devices
Plasma confinement
Stored energy
Thermonuclear reactors


 
Source Agency Technical Information Center Oak Ridge Tennessee
NTIS Subject Category 77A - Thermonuclear Fusion Devices
46G - Plasma Physics
Corporate Author Oak Ridge National Lab., TN.
Document Type Technical report
Title Note N/A
NTIS Issue Number 1323
Contract Number DE-AC05-00OR22725

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