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UID:UW-Physics-Event-6208
DTSTART:20201130T180000Z
DURATION:PT1H0M0S
DTSTAMP:20260415T005528Z
LAST-MODIFIED:20201130T205824Z
LOCATION:online
SUMMARY:Predicting Stability and Performance of Tokamak Plasmas Using 
 Flexible\, Integrated Modeling\, Plasma Physics (Physics/ECE/NE 922) S
 eminar\, Brendan Lyons\, General Atomics
DESCRIPTION:This is the annual Dalton Schnack Memorial Lecture.<br>\n
 <br>\nTokamak fusion reactors will require predictive\, integrated mo
 dels to optimize performance while maintaining robustness against disr
 uptions. The STEP (Stability\, Transport\, Equilibrium\, & Pedestal) m
 odule\, developed in OMFIT\, predicts stable equilibria self-consisten
 tly with core-transport and pedestal calculations by coupling together
  the following codes: ONETWO\, TGYRO\, EFIT\, CHEASE\, EPED\, DCON\, G
 ATO\, and CHEF (a current-drive\, heating\, & fueling module). Each co
 de reads and writes data from a centralized IMAS data structure\, allo
 wing codes to be run in arbitrary order and enabling open-loop\, feedb
 ack\, and optimization workflows. Core-pedestal calculations with STEP
  have been validated against the equilibria and profiles of individual
  DIII-D discharges and the confinement times of the H98\,y2 database. 
 In addition\, such workflows have been used to assess performance in I
 TER and the suppression of turbulence in DIII-D negative-triangularity
  plasmas. Recent enhancements to STEP have permitted accurate simulati
 ons of more exotic scenarios\, in particular a negative-central-shear 
 DIII-D scenario. In the near future\, STEP calculations of stability i
 n existing and planned tokamak scenarios will allow for the optimizati
 on of heating and current drive to maximize plasma pressure while main
 taining MHD stability.
URL:https://www.physics.wisc.edu/events/?id=6208
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