کد مقاله کد نشریه سال انتشار مقاله انگلیسی نسخه تمام متن
271266 504991 2014 7 صفحه PDF دانلود رایگان
عنوان انگلیسی مقاله ISI
Plasma diagnostics at Aditya Tokamak by two views visible light tomography
ترجمه فارسی عنوان
تشخیص پلاسما در آدییتا توکاماک با دو دید کلی توموگرافی نور قابل مشاهده است
کلمات کلیدی
تشخیص پلاسما، توموگرافی نور قابل مشاهده الگوریتم سازگار
موضوعات مرتبط
مهندسی و علوم پایه مهندسی انرژی مهندسی انرژی و فناوری های برق
چکیده انگلیسی


• Improved algorithm works equally well for central as well as for peripherical plasma regions.
• Entropy optimized smoothening parameters eliminate user dependencies.
• Real time fusion grade plasma diagnostics images.

This visible light computerized tomography exercise is a part of a project to establish an auxiliary imaging method to assist other imaging facilities at the Institute of Plasma Research (IPR), India. Space constraints around Aditya Tokamak allow only two orthogonal ports. Each port has one detector array (64 sensors) sensitive to the visual spectrum emitted by Hα emission. The objective here is to report the developments on limited view tomography for hot plasma imaging. Spatially filtered entropy maximization algorithm with non-uniform discretization grids is employed. Estimation of unique kernel smoothening parameters (mask size and exponent factor) depends on entropy function and projection data. It removes requirement of any arbitrary/user-based decision for choosing a regularization factor thus minimizes the chance for biasedness or errors. Synthetic projection data is used to analyse the performance of this modification. The error band in the process of recovery remains under acceptable level (less than 15%) irrespective of the origin of the emissions from the core. Reconstructed hot plasma images/profiles from Aditya Tokamak are shown. These profiles may improve the current understanding about (a) plasma–wall interaction or edge plasma turbulence, (b) control and generation of plasma and (c) correlations between theoretical and engineering advancements in Tokamak reactors.

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ناشر
Database: Elsevier - ScienceDirect (ساینس دایرکت)
Journal: Fusion Engineering and Design - Volume 89, Issue 11, November 2014, Pages 2659–2665
نویسندگان
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