9
Views
6
CrossRef citations to date
0
Altmetric
Technical Paper

A Comparison of Sphere-Pac and Pellet (U,Pu)O2 Fuel Pins in Low-Burnup Instrumented Irradiation Tests

&
Pages 26-38 | Published online: 13 May 2017

References

  • R. A. BRADLEY, Fuels and Materials Development Program Quarterly Progress Report, September 30, 1969, ORNL-4480, pp. 6–8, Oak Ridge National Laboratory (1969).
  • F. G. KITTS, R. B. FITTS, and A. R. OLSEN, “Sol-Gel Urania-Plutonia Microsphere Preparation and Fabrication into Fuel Rods,” Intern. Symp. Plutonium Fuels Technol., Scottsdale, Ariz., 1967, Nucl. Met., 13, 195, American Institute of Mining, Metallurgical, and Petroleum Engineers, New York (1968).
  • D. B. TRAUGER, “Some Major Fuel Irradiation Test Facilities of the Oak Ridge National Laboratory,” ORNL-3574, Oak Ridge National Laboratory (1964).
  • R. B. FITTS, J. L. MILLER, Jr., and E. L. LONG, Jr., “Observations on Tungsten-Rhenium Thermocouples Used In-Reactor in (U,Pu)O2 Fuel Pins,” ORNL-TM-3617, Oak Ridge National Laboratory (1972); also, Proc. 5th Symp. Temperature, Its Measurement and Control in Science and Industry, Washington, D.C. (1971).
  • C. M. COX and F. J. HOMAN, “PROFIL—A One Dimensional FORTRAN IV Program for Computing Steady-State Temperature Distribution In Cylindrical Ceramic Fuels,” ORNL-TM-2443, Oak Ridge National Laboratory (March 1969) and Addendum (August 1969).
  • W. E. BAILY et al., “Thermal Conductivity of Uranium-Plutonium Oxide Fuels,” Intern. Symp. Plutonium Fuels Technol., Scottsdale, Ariz., 1967, Nucl. Met., 13, 293, Americal Institute of Mining, Metallurgical, and Petroleum Engineers, New York (1968).
  • C. N. CRAIG et al., “Heat Transfer Coefficients Between Fuel and Cladding In Oxide Fuel Rods,” GEAP-5748, General Electric Co. (1969).
  • C. M. COX, D. R. CUNEO, and E. J. MANTHOS, “Performance of Sphere-Pac and Pelletized (U,Pu)O2 During Severe Overpower Transients,” Proc. Conf. Fast Reactor Fuel Element Technology, pp. 701–724, American Nuclear Society, Hinsdale, Illinois (1971).
  • A. R. OLSEN, R. B. FITTS, and W. J. LACKEY, “In-Reactor Restructuring Temperatures and Kinetics for (U,Pu)O2,” ORNL-TM-3387, Oak Ridge National Laboratory (1971); also, Proc. Conf. Fast Reactor Fuel Element Technology, pp. 579–602, American Nuclear Society, Hinsdale, Illinois (1971).
  • R. B. FITTS, E. L. LONG, Jr., and J. M. LEITNAKER, “Observations of Fuel-Cladding Chemical Interactions as Applied to GCBR Fuel Rods,” ORNL-TM-3385, Oak Ridge National Laboratory (1971); also, Proc. Conf. Fast Reactor Fuel Element Technology, pp. 431–458, American Nuclear Society, Hinsdale, Illinois (1971).
  • R. B. FITTS and F. L. MILLER, “Analysis and Performance of Instrumented Fuel Pins,” Trans. Am. Nucl. Soc., 15, 180 (1972).
  • F. L. MILLER and R. B. FITTS, “Statistical Analysis of SG-3 Data,” ORNL-TM-4034, Oak Ridge National Laboratory (in preparation).
  • J. DANIEL et al., “Thermal Conductivity of UO2,” HW-69945, Hanford Works (1962).
  • Thermal Conductivity of UO2, International Atomic Energy Agency Technical Report Series, 59, 15, 44, International Atomic Energy Agency, Vienna (1966).
  • A. R. OLSEN et al., “The Fabrication and Irradiation Testing of Sol-Gel Nuclear Fuels at ORNL,” ORNL-TM-1971, pp. 21–22, Oak Ridge National Laboratory (1967).
  • H. ANDRIESEN, “Heat Transfer Inside Nuclear Fuels Consisting of Compacted UO2 and UO2-PuO2 Powders,” EURAEC-1998, United States—Euratom Joint Research and Development Program (1967).
  • G. TESTA et al., “In-Pile Fuel Studies for Design Purposes,” Nucl. Appl. Technol., 7, 12, 555 (1969).
  • H. MARCHANDISE, “Combustibilitie Thermeque Du Bioxyde d’Uranium,” EUR-4568f, European Atomic Energy Community (1970).
  • J. W. WEBER and E. D. JENSEN, “Effectof O/M on Irradiated Mixed-Oxide Stainless-Steel Cladding Compatibility,” Trans. Am. Nucl. Soc., 14, 175 (1971).
  • K. J. PERRY and C. N. CRAIG, “Austenitic Stainless-Steel Compatibility with Mixed-Oxide Fuel,” Trans. Am. Nucl. Soc., 12, 564 (1969).
  • L. HARRISON, R. C. LIIMATAINEN, and F. J. TESTA, “Photographic Studies of Metal Clad, UO2-Core Fuel Rods in TREAT,” Chemical Engineering Division Semiannual Report, July-December 1966, ANL-7325, p. 160, Argonne National Laboratory (1967).
  • E. A. AITKEN, “Thermal Diffusion in Closed Oxide Fuel Systems,” J. Nucl. Mater., 30, 62 (1969).
  • K. E. SPEAR, A. R. OLSEN, and J. M. LEITNAKER, “Thermodynamic Applications to (U,Pu)O2±x Fuel systems,” ORNL-TM-2494, Oak Ridge National Laboratory (1969).
  • W. J. LACKEY, F. J. HOMAN, and A. R. OLSEN, “Porosity and Actinide Redistribution During Irradiation of (U,Pu)O2,” ORNL-TM-3762, Oak Ridge National Laboratory (1972).
  • M. G. ADAMSON, “Thermal Diffusion of Oxygen in Hyperstoichiometric Urania with Low Carbon Content,” J. Nucl. Mater., 38, 213 (1971).

Reprints and Corporate Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

To request a reprint or corporate permissions for this article, please click on the relevant link below:

Academic Permissions

Please note: Selecting permissions does not provide access to the full text of the article, please see our help page How do I view content?

Obtain permissions instantly via Rightslink by clicking on the button below:

If you are unable to obtain permissions via Rightslink, please complete and submit this Permissions form. For more information, please visit our Permissions help page.