The design of the Tokamak Physics Experiment (TPX)

Schmidt, J.; Thomassen, K.I.; Goldston, Robert James; Neilson, G.H.; Nevins, W. M.; Sinnis, J.; Andersen, Poul Erik; Bair, W.J.; Barr, W.L.; Batchelor, D. B.; Baxi, C.B.; Berg, G.P.A.; Bernabei, S.; Bialek, J.; Bonoli, P. T.; Boozer, Allen H.; Bowers, D. L.; Bronner, G.; Brooks, J.N.; Brown, Tom; Bulmer, R.H.; Butner, D.N.; Campbell, R. B.; Casper, T. A.; Chaniotakis, Emmanouil; Chaplin, M.R.; Chen, S. J.; Chin, E.; Chrzanowski, J.; Citrolo, J.; Cole, M. J.; Dahlgren, F.; Davis, Fleet; Davis, J.W.; Davis, S.; Diatchenko, N.; Dinkevich, S.; Feldshteyn, Yakov; Felker, B.; Feng, Tao; Fenstermacher, M.E.; Fleming, Rachel; Fogarty, P.J.; Fragetta, W.; Fredd, E.; Gabler, Michael; Galambos, J.; Gohar, Y.; Goranson, P.; Greenough, N.; Grisham, L.; Haines, John; Haney, Scott W.; Hassenzahl, W.V.; Heim, J.R.; Heitzenroeder, P.; Hill, D. N.; Hodapp, T.; Houlberg, W. A.; Hubbard, A.; Hyatt, A.W.; Jackson, Mark; Jaeger, E. F.; Jardin, S.C.; Johnson, John L.; Jones, G. H.; Juliano, D. R.; Junge, Ranka; Kalish, M.; Kessel, C.; Knutson, D.; LaHaye, R.J.; Lang, D.D.; Langley, R.A.; Liew, S. L.; Lu, E.; Mantz, H.C.; Manickam, J.; Mau, T.K.; Medley, S. S.; Mikkelsen, D. R.; Miller, R.L.; Monticello, D.; Morgan, D.W.; Moroz, Paul; Motloch, Chester G.; Mueller, J.; Myatt, L.; Nelson, B.; Neumeyer, C.; Nilson, D. G.; O'Conner, T.; Pearlstein, L. D.; Peebles, W. A.; Pelovitz, M.; Perkins, F. W.; Perkins, L.J.; Petersen, D.; Pillsbury, R.D.; Politzer, Peter; Pomphrey, N.; Porkoláb, M.; Posey, A.; Radovinsky, A.; Raftopoulis, S.; Ramakrishnan, S.; Ramos, J. J.; Rauch, W.; Ravenscroft, D.; Redler, K.; Reiersen, W.; Reiman, A.; Reis, E.E.; Rewoldt, G.; Richards, D. J.; Rocco, R.; Rognlien, T. D.; Ruzic, D. N.; Sabbagh, S.A.; Sapp, J.W.; Sayer, R. O.; Scharer, J.E.; Schmitz, L.; Schnitz, J.; Sevier, L.; Shipley, S. E.; Simmons, R.T.; Slack, D.S.; Smith, Gary R.; Stambaugh, R.D.; Steill, G.; Stevenson, T. N.; Stoenescu, Stefan; Onge, K. T.St; Stotler, D.P.; Strait, T.; Strickler, D. J.; Swain, D. W.; Tang, W. M.; Tuszewski, M.; Ulrickson, M.; VonHalle, A.; Walker, M. S.; Wang, C.; Wang, P.; Warren, Joseph E.; Werley, K.A.; West, W.P.; Williams, Frances; Wong, R.L.; Wright, Kathryn; Wurden, G. A.; Yugo, J.J.; Zakharov, L.; Zbasnik, J.

doi:10.1007/bf01079667

Cited by 17 publications

(3 citation statements)

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“…A multiplicative factor of 1.5 was applied to the "standard" TSC transport coefficients [9] with 10% carbon impurity (Z EFF =2. 7) and <n e >~ 0.7×10 19 to obtain this agreement. Almost identical agreement was obtained in another run with a multiplicative factor of 1.0 but with 90% carbon impurity (Z EFF =5).…”

supporting

confidence: 60%

“…Burn control feedback and the capability of diverter sweeping were added for the BPX experiment [6]. TSC was used extensively on TPX for vertical control, shape control, and for developing plasma scenarios [7]. For ITER, TSC was used to compute volt-second consumption and shape control, and to develop plasma disturbances for evaluations of the control system [8].…”

mentioning

confidence: 99%

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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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supporting

confidence: 60%

mentioning

confidence: 99%

Tokamak Simulation Code modeling of NSTX

Jardin¹,

Kaye²,

Ménard³

et al. 2000

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“…The need for a steady state tokamak has hardly escaped the world's attention. In 1993, the Princeton Plasma Physics Lab (PPPL) put in a proposal for a steady state tokamak called tokamak physics experiment, or TPX [10]. This was proposed to be a tokamak which had its current driven only externally, by beams and/or microwaves, as well as by a characteristic of the toroidal geometry called bootstrap current.…”

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confidence: 99%

Comment on ‘The advanced tokamak path to a compact net electric fusion pilot plant’

Manheimer¹

2022

Nucl. Fusion

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This comment (letter) examines a recent GA concept which they hope will lead to a tokamak fusion pilot plant. As tokamaks are now the closest configuration to practical magnetic fusion, if they cannot do a pilot plant, almost certainly no other device can either. The conclusion is that constructing a tokamak fusion pilot plant at this time is enormously risky, and is almost certainly tremendous waste of scarce fusion resources, which could be better used on other efforts in the fusion effort.

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Magnetic fusion commercial power plants

Sheffield

1994

J Fusion Energ

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The design of the Tokamak Physics Experiment (TPX)

Cited by 17 publications

References 4 publications

Tokamak Simulation Code modeling of NSTX

Tokamak Simulation Code modeling of NSTX

Comment on ‘The advanced tokamak path to a compact net electric fusion pilot plant’

Magnetic fusion commercial power plants

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