Generic study of protective control features for superconducting Tokamak TF coil system

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The Toroidal Field (TF) coil system is a major component of a Tokamak power reactor. A reliable and safe operation of the TF coil system is therefore vital to the power plant. This paper presents a generic assessment of the safety related instrumentation and control systems needed for routine operation and for maintenance of the plant in a safe shutdown condition. The safety control requirements described here are based on the operational experiences obtained from existing superconducting magnet systems combined with the generic PSAR development for the Experimental Power Reactors. Irregularities of operation developing from electrical, mechanical or thermal malfunctions ... continued below

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Pages: 4

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Majumdar, D.; Hsieh, S.Y. & Powell, J.R. January 1, 1977.

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Description

The Toroidal Field (TF) coil system is a major component of a Tokamak power reactor. A reliable and safe operation of the TF coil system is therefore vital to the power plant. This paper presents a generic assessment of the safety related instrumentation and control systems needed for routine operation and for maintenance of the plant in a safe shutdown condition. The safety control requirements described here are based on the operational experiences obtained from existing superconducting magnet systems combined with the generic PSAR development for the Experimental Power Reactors. Irregularities of operation developing from electrical, mechanical or thermal malfunctions are analyzed and redundant controls necessary for the operation of the plant are discussed. These are described under the following nine topics: Magnet system monitoring and control, emergency shutdown system, vacuum monitoring system, cryogenic monitor system, power supply system, magnet support structure monitoring system, coil containment monitor system, air quality control system, and radiation monitoring system. It is concluded that the protective control system of a superconducting TF coil is rather complicated and should therefore be developed and implemented early in the Tokamak reactor program to ensure the safety and reliability of fusion power plants.

Physical Description

Pages: 4

Notes

Dep. NTIS, PC A02/MF A01.

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  • 7. symposium on fusion research project, Knoxville, TN, USA, 25 Oct 1977

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  • Report No.: BNL-23409
  • Report No.: CONF-771029-131
  • Grant Number: EY-76-C-02-0016
  • Office of Scientific & Technical Information Report Number: 5331379
  • Archival Resource Key: ark:/67531/metadc1070714

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Office of Scientific & Technical Information Technical Reports

Reports, articles and other documents harvested from the Office of Scientific and Technical Information.

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  • January 1, 1977

Added to The UNT Digital Library

  • Feb. 4, 2018, 10:51 a.m.

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  • April 20, 2018, 6:49 p.m.

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Majumdar, D.; Hsieh, S.Y. & Powell, J.R. Generic study of protective control features for superconducting Tokamak TF coil system, article, January 1, 1977; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc1070714/: accessed July 19, 2018), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.