Plasma diagnostics at Aditya Tokamak by two views visible light tomography
- 1. Nuclear Engineering and Technology Programme, Indian Institute of Technology, Kanpur (India)
- 2. Department of Mechanical Engineering, Indian Institute of Technology, Kanpur (India)
- 3. Institute for Plasma Research (India)
Description
Graphical abstract: - Highlights: • 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. - Abstract: 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
Availability note (English)
Available from http://dx.doi.org/10.1016/j.fusengdes.2014.07.003Additional details
Identifiers
- DOI
- 10.1016/j.fusengdes.2014.07.003;
- PII
- S0920-3796(14)00453-0;
Publishing Information
- Journal Title
- Fusion Engineering and Design
- Journal Volume
- 89
- Journal Issue
- 11
- Journal Page Range
- p. 2659-2665
- ISSN
- 0920-3796
- CODEN
- FEDEEE
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 46090383
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Quality check status
- Yes
- Descriptors DEI
- ADITYA TOKAMAK; ALGORITHMS; COMPUTERIZED TOMOGRAPHY; CONTROL; CORRELATIONS; ENTROPY; HOT PLASMA; PLASMA DIAGNOSTICS; PLASMA PRODUCTION; PLASMA RADIAL PROFILES; SENSORS; TURBULENCE; VISIBLE RADIATION;
- Descriptors DEC
- CLOSED PLASMA DEVICES; DIAGNOSTIC TECHNIQUES; ELECTROMAGNETIC RADIATION; MATHEMATICAL LOGIC; PHYSICAL PROPERTIES; PLASMA; RADIATIONS; THERMODYNAMIC PROPERTIES; THERMONUCLEAR DEVICES; TOKAMAK DEVICES; TOMOGRAPHY;
Optional Information
- Copyright
- Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.