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(IC-1) Physics Considerations in the Design of NCSX

G.H. Neilson1), M.C. Zarnstorff1), L.P. Ku1), E.A. Lazarus2), P.K. Mioduszewski2), W.A. Cooper3), M. Fenstermacher4), E. Fredrickson1), G.Y. Fu1), A. Grossman5), P.J. Heitzenroeder1), R.H. Hatcher1), S.P. Hirshman2), S.R. Hudson1), M. Isaev6), D.W. Johnson1), H.W. Kugel1), J.F. Lyon2), R. Majeski1), M. Mikhailov6), D.R. Mikkelsen1), D.A. Monticello1), H.E. Mynick1), B.E. Nelson2), N. Pomphrey1), W.T. Reiersen1), A.H. Reiman1), P.H. Rutherford1), J.A. Schmidt1), D.A. Spong2), D.J. Strickler2), A. Subbotin6)
1) Princeton Plasma Physics Laboratory, Princeton, NJ, USA
2) Oak Ridge National Laboratory, Oak Ridge, TN, USA
3) École Polytechnique Federale de Lausanne, Lausanne, Switzerland
4) Lawrence Livermore National Laboratory, Livermore, CA, USA
5) University of California at San Diego, San Diego, CA, USA
6) RRC Kurchatov Institute, Moscow, Russia

Abstract.  Compact stellarators have the potential to make steady-state, disruption-free magnetic fusion systems with $ \beta$ $ \approx$ 5% and relatively low aspect ratio (R/$ \langle$a$ \rangle$ < 4.5) compared to most drift-optimized stellarators. Magnetic quasi-symmetry can be used to reduce orbit losses. The National Compact Stellarator Experiment (NCSX) is designed to test compact stellarator physics in a high-beta quasi-axisymmetric configuration and to deter-mine the conditions for high-beta disruption-free operation. It is designed around a reference plasma with low ripple, good magnetic surfaces, and stability to the important ideal instabilities at $ \beta$ $ \approx$ 4%. The device size, available heating power, and pulse lengths provide access to a high-beta target plasma state. The NCSX has magnetic flexibility to explore a wide range of equilibrium conditions and has operational flexibility to achieve a wide range of beta and collisionality values. The design provides space to accommodate plasma-facing components for divertor operation and ports for an extensive array of diagnostics.

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IAEA 2003