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A new look at density limits in tokamaks
While the results of early work on the density limit in tokamaks from the ORMAK and DITE groups have been useful over the years, results from recent experiments and the requirements for extrapolation…
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Numerical study of tokamak equilibria with arbitrary flow
The effects of toroidal and poloidal flows on the equilibrium of tokamak plasmas are numerically investigated using the code FLOW. The code is used to determine the changes in the profiles induced by…
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Equilibrium properties of spherical torus plasmas in NSTX
Research in NSTX has been conducted to establish spherical torus plasmas to be used for high ?, auxiliary heated experiments. This device has a major radius R0 = 0.86?m and a midplane halfwidth of…
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Fusion nuclear science facilities and pilot plants based on the spherical tokamak
A fusion nuclear science facility (FNSF) could play an important role in the development of fusion energy by providing the nuclear environment needed to develop fusion materials and components. The…
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Electromagnetic transport from microtearing mode turbulence.
This Letter presents nonlinear gyrokinetic simulations of microtearing mode turbulence. The simulations include collisional and electromagnetic effects and use experimental parameters from a high-β…
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H-mode pedestal, ELM and power threshold studies in NSTX
H-mode operation plays a crucial role in National Spherical Torus Experiment (NSTX) research, allowing higher beta limits due to reduced plasma pressure peaking, and long pulse operation due to high…
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Observations of Pc 1–2 waves in the outer magnetosphere
High time resolution measurements made inside the magnetopause from L=7 to L=14 by the University of California at Los Angeles fluxgate magnetometer aboard the Ogo 5 satellite demonstrate that Pc 1–2…
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The dependence of H-mode energy confinement and transport on collisionality in NSTX
Understanding the dependence of confinement on collisionality in tokamaks is important for the design of next-step devices, which will operate at collisionalities at least one order of magnitude…
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NSTX plasma operation with a Liquid Lithium Divertor
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Aspect Ratio Scaling of Ideal No-wall Stability Limits in High Bootstrap Fraction Tokamak Plasmas
Recent experiments in the low aspect ratio National Spherical Torus Experiment (NSTX) [M. Ono et al., Nucl. Fusion 40, 557 (2000)] have achieved normalized beta values twice the conventional tokamak…
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