کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
271272 504991 2014 7 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Bootstrap current fraction scaling for a tokamak reactor design study
ترجمه فارسی عنوان
مقیاس کسری جریان جاری بوت استرپ برای مطالعه طراحی راکتی توکاماک
کلمات کلیدی
کسری جریان جاری بوت استرپ، کدهای سیستم، طراحی راکتور، توکاماک، توکامک کروی، مقیاس گیری
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
چکیده انگلیسی


• New bootstrap current fraction scalings for systems codes were derived by solving the Hirshman–Sigmar model.
• Nine self-consistent MHD equilibria were constructed in order to compare the bootstrap current fraction values.
• Wilson formula most successfully predicted the bootstrap current fraction, but it requires current density profile index.
• The new scaling formulas and IPDG accurately estimated the fBS values for the normal and weakly reversed shear tokamaks.

We have derived new bootstrap current fraction scalings for systems codes by solving the Hirshman–Sigmar model, which is valid for arbitrary aspect ratios and collision conditions. The bootstrap current density calculation module in the ACCOME code was used with the matrix inversion method without the large aspect ratio assumption. Nine self-consistent MHD equilibria, which cover conventional, advanced and spherical tokamaks with normal or reversed shear, were constructed using numerical calculations in order to compare the bootstrap current fraction values with those of the new model and all six existing models. The Wilson formula successfully predicted the bootstrap current fraction, but it requires current density profile index for the calculation. The new scaling formulas and IPDG accurately estimated the bootstrap current fraction for the normal and weakly reversed shear tokamaks, regardless of the aspect ratio. However, none of the existing models except the Wilson formula can accurately estimate the bootstrap current fraction for the reversed shear tokamaks, which is promising for the advanced tokamak operation mode.

ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Fusion Engineering and Design - Volume 89, Issue 11, November 2014, Pages 2709–2715
نویسندگان
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