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Technical Paper

In-Pile Thermal Conductivity of Fuel Oxide: UO2 Pellets and Vipac UO2-PuO2 Pellets and Sol-Gel

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Pages 208-216 | Published online: 10 May 2017

References

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  • H. F. HONECK, “A Thermalization Transport Theory Code for Reactor Lattice Calculation,” BNL-5826, Battelle-Northwest.
  • J. P. STORA et al., “Conductibilité thermique de l’oxide d’uranium fritté dans les conditions d’utilisation en pile,” CEA-R-2586, Commissariat a l’Energie Atomique, Paris, France (1964).
  • R. C. HAWKINGS and A. S. BAIN, “The Effect of Oxygen/Uranium Ratio on the Thermal Conductivity of Uranium Oxide During Irradiation in Pellet Rod Mark V,” AECL-1790, Atomic Energy of Canada Ltd. (1963).
  • M. F. LYONS et al., “UO2 Powder and Pellet Thermal Conductivity During Irradiation,” GEAP-5100-1, General Electric Co. (1966).
  • A. CALZA-BINI, E. FERRANTE, A. NOBILI, P. L. ROTOLONI, and G. TESTA, “Fuel Microstructure Variations as a Consequence of the First Irradiation Period and of the Ways of Approach to Power,” Energia Nucleare, 18, luglio-agosto (1971).
  • A. ANDRIESSEN, “Transport de chaleur à l’intérieur de combustibles nucléaires constitués d’UO2 et d’UO2-PuO2,” NB-6712-12 (1967).
  • R. L. GIBBY, “The Effect of Plutonium Content on the Thermal Conductivity of(U,Pu)O2 Solid Solutions,” J. Nucl. Mater., 38, 163 (1971).
  • A. CALZA BINI etal., “Comportamento dinamico di barre combustibili a UO2-PuO2 durante la salita a potenza e l’inizio della permanenza in reattore,” CNEN RT/ING(73)9, Comitato Nazionale Energia Nucleare, Italy.
  • M. D. FRESHLEY, “A Comparison of Pellet and Vipac Nuclear Fuels,” Nucl. Eng. Des., 21, 266 (1972).

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