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Computational modeling of the resistive MHD evolution of reverse-field-pinch (RFP) plasmas with boundary shaping is undertaken. The VMEC code obtains equilibria that are similar to quasi-single helicity (QSH) states in an RFP with a helical axis and a symmetric boundary [J.D. Hanson, et al., Nuclear Fusion 53, 083016 (2013)]. Previous work has shown that axisymmetric boundary shaping affects whether an axisymmetric or QSH equilibrium is obtained in VMEC and it affects the extent of the swing of the helical axis in the QSH state. In this work, these equilibria are used as initial conditions for the NIMROD code [C.R. Sovinec, et al., Phys. Plasmas 10, 1727 (20030]. Resistive MHD behavior will be explored and particular attention will be paid to the evolution of global tearing modes in both axisymmetric and helical equilibria.

* This work is supported by the U.S. Department of Energy under Grant DE-FG02-03ER54699 at the University of Montana.


Plasma Physics, Computational Physics, NIMROD, Reversed Field Pinch, Quasi-Single Helicity


This poster was presented at the American Physical Society, Division of Plasma Physics Meeting in Portland, Oregon, November 5-9, 2018.

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