A blister divertor for tokamaks
نویسندگان
چکیده
منابع مشابه
On the difference of H-mode power threshold in divertor and limiter tokamaks
The difference in the H-mode power threshold in divertor and limiter configurations is numerically investigated by analysing the effect of boundary conditions imposed on the last closed magnetic surface (LCMS) and given by prescribed density and temperature e-folding lengths, δn and δT , respectively. It is demonstrated that the variation of δn and δT significantly affects the H-mode power thre...
متن کاملLow frequency heating and flow driven by the dynamic ergodic divertor in tokamaks
The profile and dissipation of the field excited by dynamic ergodic divertor (DED) coils in tokamak plasmas are calculated, and an estimate is made of the poloidal/toroidal velocities driven by this field. The coils are idealized as an inboard sheet current composed of a toroidal sequence of helical line current segments expanded in Fourier series with poloidal/toroidal mode numbers M/N , and m...
متن کاملEffects of Large Aspect Ratios and Fluctuations on Hard X-Ray-Detection in Lower Hybrid Driven Divertor Tokamaks
This Article is brought to you for free and open access by the Electrical & Computer Engineering at ODU Digital Commons. It has been accepted for inclusion in Electrical & Computer Engineering Faculty Publications by an authorized administrator of ODU Digital Commons. For more information, please contact [email protected]. Repository Citation Vahala, Linda L.; Vahala, George; and Bonoli, P...
متن کاملHow a blister heals
We use experiments to study the dynamics of the healing of a blister, a localized bump in a thin elastic layer that is adhered to a soft substrate everywhere except at the bump. We create a blister by gently placing a glass cover slip on a PDMS substrate. The pressure jump across the elastic layer drives fluid flow through micro-channels that form at the interface between the layer and the subs...
متن کاملDivertor interferometer diagnostic for ITER
In the harsh environment of the divertor region in ITER, plasmas spanning a huge density range from 1019 to 1022 m−3 are anticipated making measurement of the electron density particularly challenging. For any reasonable wavelength choice, the total phase measured by a conventional two-color interferometer system is always 2 and therefore subject to fringe counting errors. This problem can be r...
متن کاملذخیره 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: Nuclear Fusion
سال: 1978
ISSN: 0029-5515,1741-4326
DOI: 10.1088/0029-5515/18/6/016