BEGIN:VCALENDAR VERSION:2.0 CALSCALE:GREGORIAN PRODID:UW-Madison-Physics-Events BEGIN:VEVENT SEQUENCE:1 UID:UW-Physics-Event-8490 DTSTART:20231106T180000Z DTEND:20231106T191500Z DTSTAMP:20260414T012208Z LAST-MODIFIED:20231102T125742Z LOCATION:1610 Engineering Hall SUMMARY:On the physical principles of power exhaust and novel divertor solutions for tokamak fusion reactors\, Plasma Physics (Physics/ECE/N E 922) Seminar\, Prof. Ulrich Stroth\, IPP Garching\, Germany DESCRIPTION:Safe removal of the power generated in a fusion reactor wi thout damaging the inner wall elements of the device is one of the mos t important research objectives of magnetic fusion. This presentation will introduce the main physical mechanisms by which plasma energy is dissipated before it can reach the plasma-facing components\, and will explain how different divertor concepts harness them for an optimal p ower exhaust solution without compromising the performance of the core plasma.
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\nA particularly attractive divertor solution was recently proposed. It bases on the occurrence of a dense\, cold and st rongly radiation plasma volume on closed magnetic flux surfaces near t he magnetic X-point\, known as X-point radiator (XPR) [1\,2]. This phy sics of this phenomenon is well described by a reduced power balance m odel [3] and by comprehensive SOLPS-ITER transport simulations [4]. Th e XPR can be real-time controlled to maintain a high-confinement plasm a solution with mitigated edge-localized (ELMs) modes and a divertor f ully detached from the hot plasma.
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\nOnce the XPR has been created\, the magnetic configuration can be modified so that the X-poi nt comes to lie on the wall surface\, which corresponds to the compact radiative divertor (CRD) solution. In addition to the benefits of the XPR\, the CRD features a number of further advantageous characteristi cs with regard to a reactor: it works in a much simplified divertor ge ometry and results in a larger and more stable plasma. Successful CRD operation was demonstrated with high-power discharges on the ASDEX Upg rade tokamak and SOLPS-ITER simulations predict its applicability to r eactor size plasmas [5].
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\n[1] Reimold F. et al.\, Nucl. Fu sion 55\, 033004 (2015)
\n[2] Bernert M. et al.\, J. Nucl. Mater. 12\, 111 (2017)
\n[3] Stroth U. et al.\, Nucl. Fusion 62\, 076008 (2022)
\n[4] Pan\, O. et al.\, Nucl. Fusion 63 016001 (2023)
\n[5] Pan\, O. et al.\, IAEA Conference\, London\, 2023
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\ nBio:
\nProf. Ulich Stroth is a Max-Planck Director and the Head o f the Division Plasma Edge and Wall\, at the Max-Planck Institut für Plasmaphysik (IPP)\, in Garching\, Germany. In addition\, he is a full Professor at Technical University of Munich in the field of Experimen tal Plasma Physics. He earned his physics degree at the Technical Univ ersity of Darmstadt and did his PhD thesis at the Institute Laue Lange vin in Grenoble\, France. His research interests are plasma and fluid turbulence with comparisons between experiment and simulation\, microw ave applications to plasmas\, as well as plasma-wall interaction. Rece nt work addresses the development and physical understanding of sawtoo th-free plasma scenarios\, as well as comparison of specific aspects o f plasma confinement and exhaust in stellarators and tokamaks. URL:https://www.physics.wisc.edu/events/?id=8490 END:VEVENT END:VCALENDAR