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Effect of Various Control Modes on the Steady-State Full and Part Load Performance of a Direct-Cycle Nuclear Gas Turbine Power Plant PUBLIC ACCESS

[+] Author Affiliations
R. E. Covert, J. M. Krase, D. C. Morse

General Atomic Co., San Diego, CA

Paper No. 74-WA/GT-7, pp. V001T01A002; 10 pages
doi:10.1115/74-WA/GT-7
From:
  • ASME 1974 Winter Annual Meeting: GT Papers
  • ASME 1974 Winter Annual Meeting: GT Papers
  • New York, New York, USA, November 17–22, 1974
  • Conference Sponsors: International Gas Turbine Institute
  • ISBN: 978-0-7918-8001-2
  • Copyright © 1974 by ASME

abstract

The performance and principal operating characteristics of the Gas Turbine HTGR power plant are reported. The reference design of the dry cooled 1100-MW(e) power plant incorporates four helium gas turbine power conversion loops integrated into the prestressed concrete reactor vessel, which also contains the reactor and the entire primary coolant system. The reactor core is virtually the same as that for the comparable HTGR steam cycle and is operated with similar maximum fuel temperatures, resulting in a turbine inlet temperature of 1500 F (816 C). An overall plant efficiency of about 37 percent is realized with a design point cycle pressure ratio of 2.35 and with a high-effectiveness recuperator in each loop. Component performance and cycle performance calculations are discussed. The variation of plant performance with ambient temperature is described. Three distinct control modes are described which are, in order of decreasing part-load efficiency, helium inventory control, reactor outlet temperature control, and bypass flow (compressor outlet to turbine outlet) control. The latter offers the most rapid control of plant output. Also described is the standard operating control mode which combines reactor outlet temperature and bypass controls to facilitate both ramp and step load changes.

Copyright © 1974 by ASME
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