Plasma-Wall Interaction in the Open Divertor of Globus-M Spherical Tokamak

نویسندگان

  • V. K. Gusev
  • I. I. Arkhipov
چکیده

Composition, morphology and structure of the deposited (mixed) surface layers after preliminary carboboronization procedure (B/C:H layers deposition) and subsequent plasma-wall interaction in the different regions of Globus-M spherical tokamak have been analyzed. Globus-M to the best of our knowledge is unique in that its first wall is almost completely covered by RGTi protection tiles: currently about 90% of its inner vessel area facing to plasma, is covered by RGTi graphite tiles doped with 2 at.% of Ti and 0.3-0.7 at.% of Si. The mixed layer properties were examined by different diagnostic techniques (electron probe microanalysis, scanning electron microscope, X-ray diffraction, Rutherford backscattering, nuclear resonance reactions, thermal desorption spectroscopy, infrared Raman scattering, and secondary ion mass spectroscopy) after sample exposure to plasma during 3000-10000 tokamak pulses. It was found that mixed protective layers and/or deposits existed even in high flux regions (separatrix strike points). The initial composition of the protective layers formed during boronization is dramatically modified during longterm plasma-wall interaction and resulted in significant intermixing of its components with inner vessel materials. Properties of the mixed layers deposited onto the surfaces intensively interacting with plasma, as well as the composition of the mixed layers deposited in the “shadowed” zones are discussed. Deuterium retention in Globus-M tokamak was estimated relying upon the data on deuterium concentrations in the mixed layers that were measured by different methods. It is revealed that deuterium was absorbed only in the mixed layers and its concentration vanished in the bulk of the tiles. Conditions of deuterium desorption are analyzed and merits of Ti doped graphite are discussed.

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

Numerical Studies and Simulation of the Lower Hybrid Waves Current Drive by using Fokker – Planck Equation in NSST and HT-7 Tokamaks

Recent experiments on the spherical tokamak have discovered the conditions to create a powerful plasma and ensure easy shaping and amplification of stability, high bootstrap current and confinement energy. The spherical tours (ST) fusion energy development path is complementary to the tokamak burning plasma experiment such as NSTX and higher toroidal beta regimes and improves the design of a po...

متن کامل

Divertor Plasma Physics Experiments on the Diii–d Tokamak

DIVERTOR PLASMA PHYSICS EXPERIMENTS ON THE DIII–D TOKAMAK. In this paper we present an overview of the results and conclusions of our most recent divertor physics and development work. Using an array of new divertor diagnostics we have measured the plasma parameters over the entire divertor volume and gained new insights into several divertor physics issues. We present direct experimental evide...

متن کامل

Heating and Confinement Study of Globus-M Low Aspect Ratio Plasma

Results on plasma heating in experiments with neutral beam injection (NBI) and ion cyclotron resonance heating (ICRH) at the fundamental harmonic of hydrogen minority in deuterium plasma in the Globus-M spherical tokamak are presented. Numerical simulation of fast ion trajectories was performed in the plasma configurations reconstructed from magnetic measurements with the help of the EFIT code....

متن کامل

Electric field-induced plasma convection in tokamak divertors

Measurements of the electric fields, E in the DIII-D tokamak divertor region @J. C. Luxon and L. G. Davis, Fusion Technology 8, Part 2A, 441 ~1985!# are quantitatively consistent with recent computational modeling establishing that E3BT circulation is the main cause of changes in divertor plasmas with the direction of the toroidal magnetic field, BT . Extensive two-dimensional measurements of p...

متن کامل

Dynamic and static deuterium inventory in ASDEX Upgrade with tungsten first wall

Deuterium retention in the divertor tokamak ASDEX Upgrade is studied by surface analysis and gas balances. Comparing C and W plasma facing components, the deuterium content of deposits at the divertor plates is dropped by a factor of 13. At the outer divertor significant implantation into the W coating is found. Deposition at remote areas is reduced by a factor of 14. Gas balances for ITER rele...

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