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Matsuoka, Seikichi; Idomura, Yasuhiro; Satake, Shinsuke*
no journal, ,
Global full-f gyrokinetic simulations, in which the gyrokinetic equation is solved based on the first principle without the scale separation with respect to the plasma distribution function, attracted much attention in the plasma transport study. Rich physics has been revealed by the simulations in axisymmetric tokamak plasmas such as JT-60 and ITER. However, no full-f simulations in three-dimensional magnetic field equilibria such as stellarators have been reported so far due to their complicated magnetic field geometries. In this work, we extend a full-f gyrokinetic simulation code, GT5D, to treat three-dimensional magnetic equilibria. A new interface code between GT5D and a 3D equilibrium code, VMEC, are developed, in which the geometry and the magnetic field provided by VMEC code is incorporated into GT5D. It is demonstrated that the neoclassical transport physics of GT5D can successfully reproduce results of another neoclassical transport code and a theory.
Idomura, Yasuhiro
no journal, ,
This talk reviews the present status of the fusion sub-project, which has been promoted under the Post-K priority issue from 2016. In order to simulate burning plasmas in ITER, which have enormous spatio-temporal scales, the extension of existing Peta-scale plasma simulations have been addressed at different levels including computing technologies, mathematical algorithms, numerical schemes, and physics models. In particular, the project focused mainly on the development of strong scaling computational techniques and multi-time-scale physics models in order to overcome a gap of time-scales. In this talk, several examples of such multi-time-scale simulations are presented, and the present status of verification and validation studies of developed codes is discussed.
Suzudo, Tomoaki
no journal, ,
Plasma-facing materials used in future nuclear fusion reactors are exposed to high heat and high dose of radiation, and it is necessary to accurately predict the degradation of the materials. Currently, it is almost impossible to experimentally mimic the fusion reactor environment, and computational methodologies are useful for the study of mechanical property changes under such an environment. We recently obtained some new knowledge on how rhenium and osmium, which are produced from tungsten the prime candidate of the plasma-facing materials, influence the material properties under neutron irradiation. In addition, we also conducted modeling studies on how phase separation of iron-chromium alloys, a model alloy of blanket materials, cause hardening. In the current presentation, these two topics are focused.