Modeling of Neoclassical Tearing Mode Stability for Generalized Toroidal Geometry

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Neoclassical tearing modes (NTMs) can lead to disruption and loss of confinement. Previous analysis of these modes used large aspect ratio, low beta (plasma pressure/magnetic pressure) approximations to determine the effect of NTMs on tokamak plasmas. A more accurate tool is needed to predict the onset of these instabilities. As a follow-up to recent theoretical work, a code has been written which computes the tearing mode island growth rate for arbitrary tokamak geometry. It calls PEST-3 [A. Pletzer et al., J. Comput. Phys. 115, 530 (1994)] to compute delta prime, the resistive magnetohydrodynamic (MHD) matching parameter. The code also calls ... continued below

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972 Kilobytes pages

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Rosenberg, A.L.; Gates, D.A.; Pletzer, A.; Menard, J.E.; Kruger, S.E.; Hegna, C.C. et al. August 21, 2002.

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Neoclassical tearing modes (NTMs) can lead to disruption and loss of confinement. Previous analysis of these modes used large aspect ratio, low beta (plasma pressure/magnetic pressure) approximations to determine the effect of NTMs on tokamak plasmas. A more accurate tool is needed to predict the onset of these instabilities. As a follow-up to recent theoretical work, a code has been written which computes the tearing mode island growth rate for arbitrary tokamak geometry. It calls PEST-3 [A. Pletzer et al., J. Comput. Phys. 115, 530 (1994)] to compute delta prime, the resistive magnetohydrodynamic (MHD) matching parameter. The code also calls the FLUXGRID routines in NIMROD [A.H. Glasser et al., Plasma Phys. Controlled Fusion 41, A747 (1999)] for Dnc, DI and DR [C.C. Hegna, Phys. Plasmas 6, 3980 (1999); A.H. Glasser et al., Phys. Fluids 18, 875 (1975)], which are the bootstrap current driven term and the ideal and resistive interchange mode criterion, respectively. In addition to these components, the NIMROD routines calculate alphas-H, a new correction to the Pfirsch-Schlter term. Finite parallel transport effects were added and a National Spherical Torus Experiment (NSTX) [M. Ono et al., Nucl. Fusion 40, 557 (2000)] equilibrium was analyzed. Another program takes the output of PEST-3 and allows the user to specify the rational surface, island width, and amount of detail near the perturbed surface to visualize the total helical flux. The results of this work will determine the stability of NTMs in an spherical torus (ST) [Y.-K.M. Peng et al., Nucl. Fusion 26, 769 (1986)] plasma with greater accuracy than previously achieved.

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972 Kilobytes pages

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INIS; OSTI as DE00808391

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  • Other Information: PBD: 21 Aug 2002

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  • Report No.: PPPL-3740
  • Grant Number: AC02-76CH03073
  • DOI: 10.2172/808391 | External Link
  • Office of Scientific & Technical Information Report Number: 808391
  • Archival Resource Key: ark:/67531/metadc740274

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  • August 21, 2002

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  • Oct. 18, 2015, 6:40 p.m.

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  • April 18, 2016, 1:01 p.m.

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Rosenberg, A.L.; Gates, D.A.; Pletzer, A.; Menard, J.E.; Kruger, S.E.; Hegna, C.C. et al. Modeling of Neoclassical Tearing Mode Stability for Generalized Toroidal Geometry, report, August 21, 2002; Princeton, New Jersey. (digital.library.unt.edu/ark:/67531/metadc740274/: accessed June 18, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.