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Description
Plasma disruption events are responsible for the most important transient EM and thermal loads on the plasma chamber, the in-vessel components and other conducting structures neighboring the plasma. This work reviews the simulations of plasma disruption carried out, by different MHD codes, to support the design of vacuum vessel and other components in facility DTT Divertor Tokamak Test [1], that is under construction in Frascati, Italy.
DTT, in addition to its main mission in investigating the scientific and technological issues related to power and particles exhaust, can represent a significant study facility for the control and mitigation of plasma disruptions. The high attainable plasma current in safe structural conditions and the available external heating, together with the flexibility in approaching different magnetic configurations in ITER-like geometry, allow the implementation of experimental campaigns devoted to investigate different disruptions mitigation techniques, by means also of the proposed SPI and MGI systems.
This work reviews the assumptions adopted in DTT design. including the expected time evolution of the plasma in case of unmitigated and mitigated MD and VDE, the budget of disruptions allowable by design, the structural impact and the choice of the worst-case events assumed for the EM and structural analyses of the machine.
The whole set of plasma simulations has been carried out by axisymmetric MAXFEA code, and it has been integrated and benchmarked with results by JOREK, DINA, NSF and CREATE simulations. Next, EM analyses have been carried out by ANSYS to evaluate EM loads in the real 3D geometry.
[1] F. Romanelli et al., Divertor Tokamak Test facility project: status of design and implementation, 2024, Nucl. Fusion 64 112015, doi:10.1088/1741-4326/ad5740.
