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Exploration of spherical torus physics in the NSTX device

Journal Article · · Nuclear Fusion

The National Spherical Torus Experiment (NSTX) is being built at Princeton Plasma Physics Laboratory to test the fusion physics principles for the spherical torus concept at the MA level. The NSTX nominal plasma parameters are Ro = 85 cm; a = 67 cm, R/a ≥ 1.26, Bt = 3 kG, Ip = 1 MA, q(95) = 14, elongation k less than or equal to 2.2, triangularity delta ≤ 0.5 and a plasma pulse length of up to 5 s. The plasma heating/current drive tools are high harmonic fast wave (6 MW, 5 s), neutral beam injection (5 MW, 80 keV, 5 s) and coaxial helicity injection. Theoretical calculations predict that NSTX should provide exciting possibilities for exploring a number of important new physics regimes, including very high plasma beta, naturally high plasma elongation, high bootstrap current fraction, absolute magnetic well and high pressure driven sheared flow. In addition, the NSTX programme plans to explore fully non-inductive plasma startup as well as a dispersive scrape-off layer for heat and particle flux handling.

Research Organization:
Oak Ridge National Laboratory (ORNL)
Sponsoring Organization:
USDOE
DOE Contract Number:
AC02-76CH03073; AC05-00OR22725
OSTI ID:
1017351
Journal Information:
Nuclear Fusion, Journal Name: Nuclear Fusion Journal Issue: 3Y Vol. 40; ISSN 0029-5515
Publisher:
IOP Science
Country of Publication:
United States
Language:
English

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