NDLI: A survey of the Tokamak fusion test reactor (TFTR) feedback control design

Content Provider	IEEE Xplore Digital Library
Author	Gran, R. Rossi, M. Firestone, M.
Copyright Year	1980
Description	Author affiliation: Grumman Aerospace Corporation, Bethpage, New York (Gran, R.; Rossi, M.) \|\| Princeton Plasma Physics Laboratory, Princeton, N.J. (Firestone, M.)
Abstract	The TFTR is an experimental Tokamak fusion reactor being built by Princeton's Plasma Physics Laboratory for the Department of Energy. Its primary function is to demonstrate that the power that can be produced in a Deuterium Tritium reaction will exceed the power required to sustain the reaction. This will be the first Tokamak device that uses Tritium and has a large enough power density to achieve a break even in energy production. To achieve the power density requires high temperatures which are achieved by causing the current in the plasma to very rapidly increase. The high currents cause heating by the atomic losses. This ohmic heating is not sufficient, however, to achieve the required temperatures. Thus a source of high energy neutral deuterium atoms is "injected" into the plasma to cause further heating. This neutral beam heating is further supplemented with a rapid motion of the plasma (on the order of 50 m/s) to cause compression and adiabatic heating. Each of these heating effects, combined with the problem of initiating a plasma at the start of the reaction, imposes severe control problems because plasma current, position, and temperature are interrelated quantitites. The Plasma Current and Plasma Position feedback control were developed using linear optimal control theory. This paper surveys the results that guarantee when the control system is implemented on the actual machine, the control will be satisfactory. To this end, simulation and design models with eddy currents, plasma current diffusion, and plasma heating have been developed. The resulting control designs are shown to be very insensitive to modeling uncertainties.
Starting Page	796
Ending Page	801
File Size	507452
Page Count	6
File Format	PDF
DOI	10.1109/CDC.1980.271912
Language	English
Publisher	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Publisher Date	1980-12-10
Publisher Place	USA
Access Restriction	Subscribed
Rights Holder	Institute of Electrical and Electronics Engineers, Inc. (IEEE)
Subject Keyword	Tokamaks Testing Inductors Feedback control Fusion reactor design Plasma temperature Heating Plasma simulation Plasma sources Plasma devices
Content Type	Text
Resource Type	Article

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1	Ministry of Education (GoI), Department of Higher Education	Sanctioning Authority	https://www.education.gov.in/ict-initiatives
2	Indian Institute of Technology Kharagpur	Host Institute of the Project: The host institute of the project is responsible for providing infrastructure support and hosting the project	https://www.iitkgp.ac.in
3	National Digital Library of India Office, Indian Institute of Technology Kharagpur	The administrative and infrastructural headquarters of the project	Dr. B. Sutradhar bsutra@ndl.gov.in
4	Project PI / Joint PI	Principal Investigator and Joint Principal Investigators of the project	Dr. B. Sutradhar bsutra@ndl.gov.in Prof. Saswat Chakrabarti will be added soon
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