Digital plasma control system and Alcasim simulation code for Alcator C-Mod

Includes bibliographical references (p. 105-107).

Bibliographic Details
Main Author: Ferrara, Marco, Ph. D. Massachusetts Institute of Technology
Other Authors: Ian H. Hutchinson.
Format: Thesis
Language:eng
Published: Massachusetts Institute of Technology 2006
Subjects:
Online Access:http://hdl.handle.net/1721.1/34452
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author Ferrara, Marco, Ph. D. Massachusetts Institute of Technology
author2 Ian H. Hutchinson.
author_facet Ian H. Hutchinson.
Ferrara, Marco, Ph. D. Massachusetts Institute of Technology
author_sort Ferrara, Marco, Ph. D. Massachusetts Institute of Technology
collection MIT
description Includes bibliographical references (p. 105-107).
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spelling mit-1721.1/344522022-01-26T16:19:04Z Digital plasma control system and Alcasim simulation code for Alcator C-Mod Ferrara, Marco, Ph. D. Massachusetts Institute of Technology Ian H. Hutchinson. Massachusetts Institute of Technology. Dept. of Nuclear Engineering. Massachusetts Institute of Technology. Department of Nuclear Engineering Massachusetts Institute of Technology. Department of Nuclear Science and Engineering Nuclear Engineering. Includes bibliographical references (p. 105-107). Thesis (S.M.)--Massachusetts Institute of Technology, Dept. of Nuclear Engineering, 2005. Abstract The Alcator C-Mod control system was upgraded to digital architecture DPCS (Digital Plasma Control System). The main features of the digital system are the high flexibility, robustness and maintainability. The hardware consists of low-latency digitizers, a single processor Xeon server and DAC output cards. The software is a set of IDL routines. In the current version of the software, DPCS is emulating the PID controller of the previous control system Hybrid, but some advanced and adaptive features have already been implemented, for example the compensation of the input offsets. DPCS has been operating successfully since the beginning of the 2004-2005 experimental campaign. One of the advantages of a digital control system is that a simulator can be embedded in the system. We programmed a Matlab-Simulink simulator Alcasim for Alcator C-Mod. The simulator is a versatile tool to model the tokamak and the plasma, to interface with the database of the real experiments and to test new control algorithms, while running open loop and closed loop simulations. The powerful block-diagram language of Simulink allows to easily update the various components of the feedback loop, should the need arise. Preliminary results from the simulations of real shots are presented and discussed. by Marco Ferrara. S.M. 2006-11-07T12:12:35Z 2006-11-07T12:12:35Z 2005 2005 Thesis http://hdl.handle.net/1721.1/34452 70691821 eng M.I.T. theses are protected by copyright. They may be viewed from this source for any purpose, but reproduction or distribution in any format is prohibited without written permission. See provided URL for inquiries about permission. http://dspace.mit.edu/handle/1721.1/7582 107 p. 5056054 bytes 5060494 bytes application/pdf application/pdf application/pdf Massachusetts Institute of Technology
spellingShingle Nuclear Engineering.
Ferrara, Marco, Ph. D. Massachusetts Institute of Technology
Digital plasma control system and Alcasim simulation code for Alcator C-Mod
title Digital plasma control system and Alcasim simulation code for Alcator C-Mod
title_full Digital plasma control system and Alcasim simulation code for Alcator C-Mod
title_fullStr Digital plasma control system and Alcasim simulation code for Alcator C-Mod
title_full_unstemmed Digital plasma control system and Alcasim simulation code for Alcator C-Mod
title_short Digital plasma control system and Alcasim simulation code for Alcator C-Mod
title_sort digital plasma control system and alcasim simulation code for alcator c mod
topic Nuclear Engineering.
url http://hdl.handle.net/1721.1/34452
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