Abstract Details
Abstracts
Author: Xianzhu Tang
Requested Type: Poster
Submitted: 2022-03-04 19:33:32
Co-authors: The TDS SciDAC Team
Contact Info:
Los Alamos National Laboratory
T-5 Applied Math & Plasma Phys
Los Alamos, NM 87545
USA
Abstract Text:
Tokamak disruption mitigation requires an integrated solution to (1) accommodate the plasma thermal energy release, also known as a thermal quench, under the constraint of acceptable first wall damage, and (2) to suppress the runaway generation if possible, or terminate the runaway current without inflicting unacceptable damage on the first wall, as well as (3) to limit the electro- magnetic forces on the blanket and vessel due to inductively driven wall current. While ITER’s disruption mitigation approach has focused on pellet injection using a combination of low-Z and high-Z atoms, other approaches such as inductively charged 3D field coils for sustained 3D magnetic perturbation and wave injections have also been considered. The TDS SciDAC Project has been developing the physics understanding of topical and coupled physics, and coming up with advanced simulations to address them. Here we report progress toward a whole device modeling capability for tokamak disruption simulation that aims to explore physics paths toward effective mitigation. New physics understandings and computational capabilities in the area of whole device MHD including the wall/blanket/vessel feedback, collisional radiative modeling accounting for relativistic electrons and same/cross species charge exchange, runaway dynamics in momentum space, and the physics of plasma thermal quench, will be reported. Potentials and critical issues with various proposed mitigation strategies will be discussed as well.
TDS SciDAC Project is jointly supported by the Office of Fusion Energy Sciences and Office of Advanced Scientific Computing Research.
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