Physics Aspects of the Compact Ignition Tokamak

Post, D.; Houlberg, W. A.; Bateman, G.; Bromberg, L.; Cohn, D.R.; Colestock, P.; Hughes, M.H.; Ignat, D.; Izzo, R.; Jardin, S.C.; Kieras‐Phillips, C.; Ku, L. P.; Kuo-Petravic, G.; Lipschultz, B.; Parker, R.; Paulson, C.C.; Peng, Yongzheng; Petravić, M.; Phillips, Michael W.; Pomphrey, N.; Schmidt, J.; Strickler, D. J.; Todd, A.M.M.; Uckan, N. A.; White, R. B.; Wolfe, S.; Young, K. M.

doi:10.1088/0031-8949/1987/t16/011

Cited by 21 publications

(17 citation statements)

References 12 publications

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“…it restricts the value of TITE (n is the plasma density, TJJ is the energy confinement time) that can be achieved. In fact, transport simulations of two recent reactor designs' and the Compact Ignition Tokamak 2,3 (CIT) do not predict ignition with an L-mode -* scal ing for TE when the density is required to remain below that predicted by present expressions for the density limit. Several formulas for the density limit are now in use, and most match recent data very well.…”

Section: Introductionmentioning

confidence: 98%

“…Greenwald has recently made an attempt to consolide the data from machines of various shapes and sizes. 9,10 He concluded that a tokamak with a high power density, low impurity level, and efficient central fuelling is limited to a density n^G = KJ X 10 2O m~3, where *c is the plasma elongation and J is the average plasma current density (in MA/m 2 ). Compared to present Hugill-type scalings, this expression tends to be more favorable for highly elongated reac:or designs.…”

Section: Introductionmentioning

confidence: 99%

“…max -2BTIRq c , where (/" = ~]0. 2 KDT/ RI p is referred to as the engineering safety factor. Nute that we express BT in T, a (the plasma minor radius) and R in m, and / p (the plasma current) in MA.…”

Section: Introductionmentioning

confidence: 99%

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Transport simulations of a density limit in radiation-dominated tokamak discharges—profile effects

Stotler

1988

The Physics of Fluids

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The density limit observed in tokamak experiments is thought to be due to a radiative collapse of the current channel. A transport code coupled with an MHD equilibrium routine is used to determine the detailed, self-consistent evolution of the plasma profiles in tokamak discharges with radiated power close to or equalling the input power. The present work is confined to ohmic discharges in steady state. It is found that the shape of the density profile can have a significant impact on the variation of the maximum electron density with plasma current. Analytic calculations confirm this result.

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Section: Introductionmentioning

confidence: 98%

Section: Introductionmentioning

confidence: 99%

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Transport simulations of a density limit in radiation-dominated tokamak discharges—profile effects

Stotler

1988

The Physics of Fluids

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“…(S), is motivated by the early work on the subject 17 and assumptions made in previous discussions of CIT. 33 At that time, 33 h = 1.5 was considered an effective description of the data. The actual experimental observation is that the maximum density increases with current.…”

Section: Ivf Hugill Coefficient Hmentioning

confidence: 99%

Ignition probabilities for Compact Ignition Tokamak designs

Stotler¹,

Goldston²

1989

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“…It was used on the TCV experiment for the design of a tokamak with a flexible shaping system, and to study doublet formation [3]. For CIT and Ignitor, it has been used to compute < [4]. TSC has been used in modeling shape control, VDEs, and volt-second benchmarking in the DIII-D experiment [5].…”

mentioning

confidence: 99%

Tokamak Simulation Code modeling of NSTX

Jardin¹,

Kaye²,

Ménard³

et al. 2000

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The Tokamak Simulation Code [TSC] is widely used for the design of new axisymmetric toroidal experiments. In particular, TSC was used extensively in the design of the National Spherical Torus eXperiment [NSTX]. We have now benchmarked TSC with initial NSTX results and find excellent agreement for plasma and vessel currents and magnetic flux loops when the experimental coil currents are used in the simulations. TSC has also been coupled with a ballooning stability code and with DCON to provide stability predictions for NSTX operation. TSC has also been used to model initial CHI experiments where a large poloidal voltage is applied to the NSTX vacuum vessel, causing a force-free current to appear in the plasma. This is a phenomenon that is similar to the "plasma halo current" that sometimes develops during a plasma disruption.TSC models the evolution of free-boundary axisymmetric toroidal plasma on the resistive and energy confinement time scales. The plasma equilibrium and field evolution equations are solved on a two-dimensional Cartesian grid. Boundary conditions between plasma/vacuum/conductors are based on the fact that the poloidal flux is continuous across interfaces. The surface-averaged transport equations for the pressures and densities are solved in magnetic flux coordinates using matrix implicit methods. An arbitrary transport model can be used. Neoclassical-resistivity, bootstrap-current, auxiliary-heating, current-drive, alpha-heating, radiation, pelletinjection, sawtooth, and ballooning-mode transport models are all available. As an option, circuit equations are solved for all the poloidal field coil systems with the effects of induced currents in passive conductors included. Realistic feedback systems can be defined to control the time evolution of the plasma current, position, and shape. Open field lines can be included, and the halo current is computed as part of the calculation.TSC can be run in several operating modes. The time dependent one-dimensional functions for the pressure p(ψ,t), the density n(ψ,t), and the effective charge state Z(ψ,t) can either be specified as input or be calculated from transport equations, density evolution equations, or impurity transport and ionization physics. The plasma current is calculated self-consistently from the changing external coil currents, with or without feedback systems included. There is also an option to impose symmetry about the midplane or to model the full device with no up/down symmetry.TSC development has been project driven. Capabilities were added as needed. TSC had its origins in the S-1 spheromak in modeling the inductive formation using a flux core [1]. It was used on the PBX experiment to calculate the effect of strong shaping on plasma axisymmetric stability, disruption forces on the passive stabilizers, voltsecond benchmarking, and in modeling the current-drive experiments [2]. It was used on the TCV experiment for the design of a tokamak with a flexible shaping system, and to study doublet formation [3]. For CIT and Ignitor, it has ...

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Physics Aspects of the Compact Ignition Tokamak

Cited by 21 publications

References 12 publications

Transport simulations of a density limit in radiation-dominated tokamak discharges—profile effects

Transport simulations of a density limit in radiation-dominated tokamak discharges—profile effects

Ignition probabilities for Compact Ignition Tokamak designs

Tokamak Simulation Code modeling of NSTX

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