Toward a first-principles integrated simulation of tokamak edge plasmas

نویسندگان

  • C S Chang
  • J Cummings
  • R. Samtaney
چکیده

Performance of the ITER is anticipated to be highly sensitive to the edge plasma condition. The edge pedestal in ITER needs to be predicted from an integrated simulation of the necessary firstprinciples, multi-scale physics codes. The mission of the SciDAC Fusion Simulation Project (FSP) Prototype Center for Plasma Edge Simulation (CPES) is to deliver such a code integration framework by (1) building new kinetic codes XGC0 and XGC1, which can simulate the edge pedestal buildup; (2) using and improving the existing MHD codes ELITE, M3D-OMP, M3D-MPP and NIMROD, for study of large-scale edge instabilities called Edge Localized Modes (ELMs); and (3) integrating the codes into a framework using cutting-edge computer science technology. Collaborative effort among physics, computer science, and applied mathematics within CPES has created the first working version of the End-to-end Framework for Fusion Integrated Simulation (EFFIS), which can be used to study the pedestal-ELM cycles.

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

The Anomalous Transport in Turbulent Plasmas

The particle and energy transport was analyzed for different regions and regimes of the plasma in tokamak with special attention for ITER. For the particle transport in the tokamak edge plasma was obtained results useful for the qualitative cross-check of the numerical models of the first principle simulations, including ITER, as well as in the elaboration of the simplified, reduced models of t...

متن کامل

Comparison of Simulation and Experimental Temperature Profiles in L-Mode Tokamak Plasmas Using an Improved Multi-Mode Model

Simulations of DIII-D, JET and TFTR L-mode tokamak plasmas are carried out using the PTRANSP predictive integrated modeling code. The simulation and experimental temperature profiles are compared. The time evolved temperature profiles are computed utilizing the Multi-Mode anomalous transport model version 7.1 (MMM7.1) which includes transport associated with drift-resistive-inertial ballooning ...

متن کامل

A novel flexible field-aligned coordinate system for tokamak edge plasma simulation

Tokamak plasmas are confined by amagnetic field that limits the particle and heat transport perpendicular to the field. Parallel to the field the ionised particles canmove freely, so to obtain confinement the field lines are ‘‘closed’’ (i.e. form closed surfaces of constant poloidal flux) in the core of a tokamak. Towards, the edge, however, the field lines intersect physical surfaces, leading ...

متن کامل

HCI Issues in Tokamak Fusion Plasmas

Thermonuclear fusion powers our universe and is a most promising option for electricity and hydrogen fuel generation within a future sustainable and environmentally benign energy scenario. We shortly describe the current status of magnetic fusion research on its way to the international tokamak experiment ITER, for which construction at the European site Cadarache (France) starts in the near fu...

متن کامل

Impurity Behavior in ITER and Helical Burning Plasmas with Internal Transport Barriers

The impurity transport simulation code TOTAL (TOroidal Transport Analysis Linkage) consisting of 1-D(dimensional) transport and 2or 3-D equilibrium is developed for analyzing tokamak and helical burning plasmas controlled by feedback scheme with gas puffing, pellet fueling injection and heating power modulations. In this code multi-species of impurity ions can be treated including neoclassical ...

متن کامل

ذخیره در منابع من


  با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید

برای دانلود متن کامل این مقاله و بیش از 32 میلیون مقاله دیگر ابتدا ثبت نام کنید

ثبت نام

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

عنوان ژورنال:

دوره   شماره 

صفحات  -

تاریخ انتشار 2008