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Technical Paper

A High-Breeding Fast Reactor with Fission Product Gas Purge/Tube-in-Shell Metallic Fuel Assemblies

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Pages 305-329 | Published online: 13 May 2017

References

  • M. C. BILLONE et al., “Status of Fuel Element Modeling Codes for Metallic Fuels,” Proc. Int. Conf. Reliable Fuel for Liquid Metal Reactors, Tucson, Arizona, September 7–11, 1987, p. 5.
  • M. BERLIN et al., “Evaluation of Sodium Retention Factors for Fission Products and Fuel,” Proc. Int. Topl. Mtg. Liquid-Metal Fast Breeder Reactor Safety and Related Design and Operational Aspects, Lyons, France, September 5–9, 1982, Vol. 3, p. 369, SFEN (1982).
  • H. TAKANO and Y. ISHIGURO, “Production and Benchmark Test of Group Constant Set, JFS-3J2,” JAERI-M 82-135, Japan Atomic Energy Research Institute (1982).
  • H. TAKANO, Japan Atomic Energy Research Institute, Private Communication (1988).
  • IAEA IWGFR/14/Rev. 1, International Atomic Energy Agency (Mar. 1979).
  • Y. I. CHANG, Argonne National Laboratory, Private Communication (Jan. 26, 1987).
  • F. A. GARNER, “Recent Insights on the Swelling and Creep of Irradiated Austenitic Alloys,” J. Nucl. Mater., 122 & 123, 459 (1984).
  • G. J. O’NEILL, “A Technical and Economic Evaluation of Vented Fuel for Sodium-Cooled Fast Ceramic Reactors,” GEAP-4770, General Electric Company (1965).

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