Two-dimensional modeling of disruption mitigation by gas injection

• Published in: Fusion engineering and design Vol. 86; no. 9; pp. 1616 - 1619
• Main Authors: Landman, I.S., Pestchanyi, S.E., Igitkhanov, Y., Pitts, R.
• Format: Journal Article Conference Proceeding
• Language: English
• Published: Amsterdam Elsevier B.V 01-10-2011; Elsevier
• Subjects: Applied sciences; Computer simulation; Controled nuclear fusion plants; Core loss; Disruption; Energy; Energy. Thermal use of fuels; Exact sciences and technology; Gas injection; Installations for energy generation and conversion: thermal and electrical energy; Massive gas injection; Noble impurity; Numerical modeling; Rare gases; Thermal conductivity; Tokamak devices; Validation; Walls; Massive gas injection; Numerical modeling; Validation; Noble impurity; Tokamak; Plasma; Impurity; Gas injection; Modeling; Contamination; Nuclear fusion reactor; Thermal conductivity; Noble gas; Disruption; Argon; Reactor core; Damaging
• ISSN: 0920-3796; 1873-7196
• DOI: 10.1016/j.fusengdes.2010.12.017

In ITER, wall damage after the disruptions can be mitigated using preventive massive gas injection (MGI) of noble gases into confined plasma. In the plasma the injected gas gets ionized and the core contamination results in fast loss of energy by radiation which distributes the wall load in a propitious way. For the modeling of MGI the tokamak code TOKES has been applied. This work reports further development of its models. The simulations earlier limited by the confinement region are expanded over the whole vessel of arbitrary wall shape. A simplified plasma model earlier employed for MGI is replaced by more adequate radiative model with dynamically changing level populations of plasma species. The processes in the plasma such as longitudinal motion, cross thermal conductivity and striking the wall are simulated neglecting wall response. The upgraded code is validated against an argon injection experiment of tokamak DIII-D.