Plasma–neutral interaction in tokamak divertor for ‘‘gas box’’ neutral model

نویسندگان
چکیده

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

اگر عضو سایت هستید لطفا وارد حساب کاربری خود شوید

منابع مشابه

Fuel Retention in the Gas Box Divertor of Jet

Components of the JET Mk-II Gas Box divertor have been analysed ex-situ after 18 months of operation with that divertor structure. The aim was to give an account on the distribution of the retained fuel along the poloidal crosssection of the divertor and, in particular, in the septum. Inside the gas box thick hydrogenated deposits were formed only on surfaces located in the near-plasma region f...

متن کامل

Divertor design for the tokamak physics experiment

In this paper we discuss the divertor design for the planned TPX tokamak, which will explore the physics and technology of steady state (1000 s pulses) heat and particle removal in high confinement (up to 4 × L-mode), high beta (up to /3 N = 5) divertor plasmas sustained by non-inductive current drive. TPX will operate in the double-null divertor configuration, with actively cooled graphite tar...

متن کامل

Local magnetic divertor for control of the plasma-limiter interaction in a tokamak

An experiment is described in which plasma flow to a tokamak limiter is controlled through the use of a local toroidal divertor coil mounted inside the limiter itself. This coil produces a local perturbed field Be approximately equal to the local unperturbed toroidal field B r ~ 3 kG, such that when Be adds to Br the field lines move into the limiter and the local plasma flow to it increases by...

متن کامل

Dissipative Divertor Operation in the Alcator C-mod Tokamak Dissipative Divertor Operation in the Alcator C-mod Tokamak

The achievement of large volumetric power losses (dissipation) in the Alcator C-Mod divertor region is demonstrated in two operational modes: radiative divertor and detached divertor. During radiative divertor operation, the fraction of SOL power lost by radiation is P R/PSOL0.8 with single null plasmas, n e < 2x10 20 m-3 and I < 1 MA. These plasmas sometimes have very high recycling, with nedi...

متن کامل

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

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: current...

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

ژورنال

عنوان ژورنال: Physics of Plasmas

سال: 1996

ISSN: 1070-664X,1089-7674

DOI: 10.1063/1.871910