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Nuclear Technology Volume 15, 1972 - Issue 2
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Technical Paper

Plutonium and Fission Product Redistribution in Mixed-Oxide Fuels During Irradiation

J. K. BahlBhabha Atomic Research Center, Bombay, India
&
M. D. FreshleyBattelle Pacific Northwest Laboratories, Richland, Washington 99352
Pages 114-124 | Published online: 12 May 2017

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Read on this site (3)

G. Giacchetti & C. Sari. (1976) Behavior of Molybdenum in Mixed-Oxide Fuel. Nuclear Technology 31:1, pages 62-69.
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R. O. Meyer, C. R. Hann & D. D. Lanning. (1975) Effects of Fissile Atom Segregation in Light Water Reactor Plutonium Recycle Fuels. Nuclear Technology 27:3, pages 389-393.
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M. D. Freshley. (1973) UO2-PUO2–A Demonstrated Fuel for Plutonium Utilization in Thermal Reactors. Nuclear Technology 18:2, pages 141-170.
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Articles from other publishers (4)

Riley J. Parrish, Xiang Liu, Alexander Winston, Jason M. Harp & Assel Aitkaliyeva. (2019) Radial microstructural evolution in low burnup fast reactor MOX fuel. Journal of Nuclear Materials 523, pages 182-188.
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Riley Parrish & Assel Aitkaliyeva. (2018) A review of microstructural features in fast reactor mixed oxide fuels. Journal of Nuclear Materials 510, pages 644-660.
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K.D. Reeve. (1975) Ceramics as nuclear reactor fuels. Ceramurgia International 1:2, pages 59-71.
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D.R. Olander. (1973) The conservation equations governing porosity and actinide redistribution in mixed-oxide fuels. Journal of Nuclear Materials 47:2, pages 251-254.
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