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UID:UW-Physics-Event-6208
DTSTART:20201130T180000Z
DURATION:PT1H0M0S
DTSTAMP:20240328T150830Z
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.
\n
\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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