MHD equilibrium and stability considerations for high-aspect-ratio ARIES-I tokamak reactors

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The requirements of an external poloidal field coil (PFC) system with minimum stored energy, double-null divertor plasmas with elongated D shape, adequate passive stabilization of plasma vertical displacement by a vacuum vessel located behind the blanket zone, and an enhanced plasma beta limit in the first stability regime are incorporated in the ARIES-I concept for a high-field tokamak reactor with high aspect ratio (A = 4.5). The plasma current and pressure profiles are also made consistent with enhanced bootstrap current I{sub bs} and reduced current drive power by means of ion cyclotron wave (ICW) or neutral beam (NB) injection. These ... continued below

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Pages: (23 p)

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Peng, Y.K.M.; Strickler, D.J.; Hogan, J.T.; Whitson, J.C.; Bathke, C.G.; Evans, K. Jr. et al. January 1, 1989.

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The requirements of an external poloidal field coil (PFC) system with minimum stored energy, double-null divertor plasmas with elongated D shape, adequate passive stabilization of plasma vertical displacement by a vacuum vessel located behind the blanket zone, and an enhanced plasma beta limit in the first stability regime are incorporated in the ARIES-I concept for a high-field tokamak reactor with high aspect ratio (A = 4.5). The plasma current and pressure profiles are also made consistent with enhanced bootstrap current I{sub bs} and reduced current drive power by means of ion cyclotron wave (ICW) or neutral beam (NB) injection. These lead to plasmas characterized by an elongation k{sub x} of 1.8 to the divertor X-point, a triangularity {delta}{sub x} of 0.7, a safety factor q on axis of q{sub 0} {approx} 1.5, a safety factor at the edge q{sub 95} > 4, a plasma beta {beta} {approx} 2%, and a poloidal beta given by {epsilon}{beta}{sub p} {approx} 0.5 ({epsilon} = 1/A). With a plasma current I{sub p} of 11 MA, a toroidal field B{sub t} of 13 T at the major radius R{sub 0} of 6.5 m, and over 3.5 m of clearance between the PFCs and the plasma edge, the stored energy in the PFC system ranges from 20 GJ during plasma operation at low beta to 12 GJ during plasma operation at high beta. 16 refs., 6 figs., 2 tabs.

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Pages: (23 p)

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NTIS, PC A03/MF A01; OSTI; INIS; GPO Dep.

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  • 13. international symposium on fusion engineering, Knoxville, TN (USA), 2-6 Oct 1989

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  • Other: DE90002152
  • Report No.: CONF-891007-22
  • Grant Number: AC05-84OR21400
  • Office of Scientific & Technical Information Report Number: 5588780
  • Archival Resource Key: ark:/67531/metadc1093937

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  • January 1, 1989

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  • Feb. 10, 2018, 10:06 p.m.

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  • April 25, 2018, 5:36 p.m.

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Peng, Y.K.M.; Strickler, D.J.; Hogan, J.T.; Whitson, J.C.; Bathke, C.G.; Evans, K. Jr. et al. MHD equilibrium and stability considerations for high-aspect-ratio ARIES-I tokamak reactors, article, January 1, 1989; Tennessee. (digital.library.unt.edu/ark:/67531/metadc1093937/: accessed October 21, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.