1 / 7

Development and application of integrated transport code to LHD plasmas

Development and application of integrated transport code to LHD plasmas. M.Yokoyama (National Institute for Fusion Science) for TASK3D collaborators. TASK3D Objectives.

damia
Download Presentation

Development and application of integrated transport code to LHD plasmas

An Image/Link below is provided (as is) to download presentation Download Policy: Content on the Website is provided to you AS IS for your information and personal use and may not be sold / licensed / shared on other websites without getting consent from its author. Content is provided to you AS IS for your information and personal use only. Download presentation by click this link. While downloading, if for some reason you are not able to download a presentation, the publisher may have deleted the file from their server. During download, if you can't get a presentation, the file might be deleted by the publisher.

E N D

Presentation Transcript

  1. Development and application of integrated transport code to LHD plasmas M.Yokoyama (National Institute for Fusion Science) for TASK3D collaborators

  2. TASK3D Objectives • Extension of integrated code (TASK) applicability to general toroidal plasmas (stellarator-heliotron plasmas) • S-H specific physics • 3D feature • Module extension/modification based on TASK • LHD experiment : • integrated analysis • prediction, operation scenario • validation

  3. Module Extension/modification LHDGauss FIT3D ER WM MORH MSSH EI VMEC HINT2 DGN/LHD NEWBOZ Stellarator-Heliotron specific physics Neoclassical (NC) diffusion (3D configuration, Er) Er determined by NC ambipolar condition NBI deposition including re-entering effects Impact of pressure driven MHD instability on pressure profile 3D feature 3D equilibrium Evolution of rotational transform instead of the current evolution (easier to include 3D effects) Heating modules incorporating 3D equilibrium

  4. TASKTASK3D: module extension/modification LHDGauss MORH TR FIT3D ER EI VMEC WM HINT2 MSSH DGN/LHD DP WR FP TX EQ Fixed-boundary equilibrium Diffusive transport BOOZER TASK Dynamic transport Kinetic transport Ray and beam tracing Full wave analysis(ICH) Wave dispersion Heating in LHD NBI analysis (Guiding Center) TASK3D NBI analysis (Re-entering) Ray tracing (ECH) current (iota) evolution radial electric field 3D Physics Neoclassical diffusion coefficient DB MHD instability’s impact on pressure profile 3D equilibrium (nested surface) 3D equilibrium (w/o nested surface assumption) 3D Equilibrium 3D equilibrium in Boozer coordinates

  5. Predictive simulation by a part of TASK3D ~ Temperature profile variation for NBI heated plasmas ~ 3D equilibrium VMEC 1D diffusion transport equation FIT3D NBI deposition Boozer TR DGN/LHD ER NC diffusion coeff. DB radial electric field Gyro-Bohm

  6. Predictive simulation by a part of TASK3D Rax=3.60m , B=-2.75T: equilibrium fixed 5 beam lines applied Density profile : fixed n0=2e19 n0=2e19 n0=4e19 n0=4e19 n0=6e19 n0=6e19 • Dedicated experiment was conducted in Sep. 2011. • Anomalous transport modelling, track of configuration change, etc.. towards increased predictability: validation study • -> Operation scenario for high-performance steady-state LHD plasmas

  7. Coordinated Working Group Meeting(CWGM) Helical Plasmas：Diversity  Systemization Joint experiment/database/analysis/papers The gateway to “3D” issues

More Related