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Technical Paper

Fission Gas Release from Uranium-Zirconium Hydride Fuel During Heating to Melting

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Pages 18-24 | Published online: 10 Apr 2017

References

  • W. P. WALLACE, M. T. SIMNAD, and B. TUROVLIN, “Fabrication and Properties of Uranium-Zirconium Hydride Fuel Elements for TRIGA Reactors,” Proc. Fuel Elements Conf., Gatlinburg, Tennessee, May 14–16, 1958, U.S. Atomic Energy Commission (1959).
  • G. L. HOFMAN and L. C. WALTERS, Materials Science and Technology, Vol. 10A, p. 88, R. W. CAHN, P. HAASEN, and E. J. KRAMER, Eds., VCH, New York (1994).
  • M. T. SIMNAD, “The U-ZrHx Alloy: Its Properties and Use in TRIGA Fuel,” E-117-833, General Atomics Company (1980).
  • N. L. BALDWIN, F. C. FOUSHEE, and J. S. GREENWOOD, “Fission Product Release from TRIGA-LEU Reactor Fuels,” GA-A16287, General Atomics Company (1980).
  • G. B. WEST, M. T. SIMNAD, and G. L. COPELAND, “Final Results from TRIGA LEU Fuel Post-Irradiation Examination and Evaluation Following Long Term Irradiation Testing in the ORR,” UZR-22, GA-A18641, General Atomics Company (1986).
  • A. F. LILLIE, D. T. McCLELLAND, W. J. ROBERTS, and J. H. WALTER, “Zirconium Hydride Fuel Element Performance Characteristics,” USAEC report AI-AEC-13084, Atomics International (1973).
  • G. R. FENSKE, J. E. EMERSON, F. E. SAVOIE, and E. W. JOHANSON, “Fission Gas Retention and Axial Expansion of Irradiated Metallic Fuel,” Proc. Int. Conf. Reliable Fuels for Liquid Metal Reactors, Tucson, Arizona, September 7–11, 1986, p. 6, American Nuclear Society (1986).
  • H. TSAI, “Fuel/Cladding Compatibility in Irradiated Metallic Fuel Pins at Elevated Temperatures,” Proc. Int. Fast Reactor Safety Mtg., Snowbird, Utah, August 12–16, 1990, Vol. II, p. 257, American Nuclear Society (1990).
  • T. B. MASSALSKI, Binary Alloy Phase Diagrams, ASM International, Materials Park, Ohio (1990).

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