BEGIN:VCALENDAR VERSION:2.0 CALSCALE:GREGORIAN PRODID:UW-Madison-Physics-Events BEGIN:VEVENT SEQUENCE:4 UID:UW-Physics-Event-4880 DTSTART:20180910T170500Z DTEND:20180910T180000Z DTSTAMP:20260308T131243Z LAST-MODIFIED:20180910T170648Z LOCATION:2241 Chamberlin Hall SUMMARY:The Advanced Tokamak Path to Steady State Fusion Energy\, Plas ma Physics (Physics/ECE/NE 922) Seminar\, Richard Buttery\, General At omics DESCRIPTION:Development of an efficient fusion reactor requires the si multaneous optimization of the plasma operating scenario and underlyin g hardware. These are inextricably linked\; an effective operating sce nario reduces demand on key components. The critical challenge is to r educe recirculating power\; if significant auxiliary heating or curren t drive is needed\, this drives up required fusion power to run these systems\, and thus size\, heat flux\, neutron load\, and cost. The Adv anced Tokamak concept addresses this through a fortuitous alignment of high plasma pressure operation with strong self-driven ‘bootstrap†™ current and low turbulent transport. Here\, research into transport\ , stability and energetic particle interactions has identified the key principles behind a solution. Further\, new integrated physics simula tions\, the first combining TGLF core\, EPED pedestal and appropriate current drive models\, show the various trade-offs and path to optimiz e the approach. Higher pressure of course increases fusion performance . But increasing the density has greater leverage\, raising the self-d riven bootstrap current and thus decreasing demand for auxiliary curre nt drive systems. Potential net-electric solutions are indicated at ~4 m radius and ~6T using conventional superconductors. However\, higher field\, high Tc superconductors provide greater margin in attainable b eta\, density\, safety factor and neutron load\, as well as easier mai ntenance and thus higher duty cycle. The plasma exhaust is managed by a combination of core radiation\, flux expansion and radiative diverto r\, tuned to ensure H mode sustainment. Divertor solutions similar to ITER are possible\, but continuous operation may require a more advanc ed configuration to reduce erosion. Overall\, studies show that well t argeted research in the coming years could validate these concepts to provide the basis to proceed with a compact Advanced Tokamak power pla nt – this talk will set out the key physics and hardware considerati ons behind its design.
\n URL:https://www.physics.wisc.edu/events/?id=4880 END:VEVENT END:VCALENDAR