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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. Subbotin^6)
 
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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