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An analytic scaling relation for the maximum tokamak elongation against n=0 MHD resistive wall modesopen access

Authors
Lee, jung pyoFreidberg, JeffreyCerfon, AntoineGreenwald, Martin
Issue Date
May-2017
Publisher
IOP PUBLISHING LTD
Keywords
MHD resistive wall mode; tokamak equilibrium; vertical elongation
Citation
NUCLEAR FUSION, v.57, no.6, pp.66051 - 66059
Indexed
SCIE
SCOPUS
Journal Title
NUCLEAR FUSION
Volume
57
Number
6
Start Page
66051
End Page
66059
URI
https://scholarworks.bwise.kr/hanyang/handle/2021.sw.hanyang/20316
DOI
10.1088/1741-4326/aa6877
ISSN
0029-5515
Abstract
A highly elongated plasma is desirable in order to increase plasma pressure and energy confinement to maximize fusion power output. However, there is a limit to the maximum achievable elongation which is set by vertical instabilities driven by the n = 0 MHD mode. This limit can be increased by optimizing several parameters characterizing the plasma and the wall. The purpose of our study is to explore how and to what extent this can be done. Specifically, we extend many earlier calculations of the n = 0 mode and numerically determine scaling relations for the maximum elongation as a function of dimensionless parameters describing (1) the plasma profile (beta(p) and l(i)), (2) the plasma shape (epsilon and delta), (3) the wall radius (b/a) and (4) most importantly the feedback system capability parameter gamma T-w. These numerical calculations rely on a new formulation of n = 0 MHD theory we recently developed (Freidberg et al 2015 J. Plasma Phys. 81 515810607, Lee et al 2015 J. Plasma Phys. 81 515810608) that reduces the 2D stability problem into a 1D problem. This method includes all the physics of the ideal MHD axisymmetric instability while reducing the computation time significantly, so that many parameters can be explored during the optimization process. The scaling relations we present include the effects of the optimal triangularity and the finite aspect ratio on the maximum elongation, and can be useful for determining optimized plasma shapes in current experiments and future tokamak designs.
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