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Thermal Evaluations for Next Generation Nuclear Plant Fuel Testing

[+] Author Affiliations
Richard G. Ambrosek, Debbie J. Utterbeck

Idaho National Engineering and Environmental Laboratory (INEEL), Idaho Falls, ID

Brandon Miller

Idaho State University, Idaho Falls, ID

Paper No. HT-FED2004-56150, pp. 43-50; 8 pages
doi:10.1115/HT-FED2004-56150
From:
  • ASME 2004 Heat Transfer/Fluids Engineering Summer Conference
  • Volume 4
  • Charlotte, North Carolina, USA, July 11–15, 2004
  • Conference Sponsors: Heat Transfer Division and Fluids Engineering Division
  • ISBN: 0-7918-4693-8 | eISBN: 0-7918-3740-8
  • Copyright © 2004 by ASME

abstract

The DOE Advanced Fuel Cycle Initiative and Generation IV reactor programs are developing new fuel types for use in the current Light Water Reactors and future advanced reactor concepts. The Advanced Gas Reactor program is planning to test fuel to be used in the Next Generation Nuclear Plant (NGNP) nuclear reactor. Preliminary information for assessing performance of the fuel will be obtained from irradiations performed in the Advanced Test Reactor large “B” experimental facility.

Copyright © 2004 by ASME

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