Magnetic equilibrium and transport modeling of divertors for solutions to exhaust problems in tokamaks
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Problems of intense exhaust heat and particle fluxes incident on material surfaces are obstacles for magnetic confinement fusion in tokamaks. Advanced divertors offer magnetic solutions to the problems by (a) increasing the plasma-wetted area via flux expansion at the targets, (b) increasing the connection length and (c) in the case of X-divertors opening regimes of stable, detached operation via poloidal flaring. By magnetic equilibrium modeling using CORSICA code, X-divertors appear feasible on NSTX-U tokamak, requiring no hardware change and respecting coil current limits. Transport simulations using SOLPS code on NSTX-U have demonstrated the advantages of the X-divertor over the standard divertor: reducing target heat and particle fluxes, achieving detachment with a lower upstream density and stabilizing the detachment front near the target.