Radial distribution of the burnup and content of plutonium in VVÉR fuel pellets

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Springer Publishing Company

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Effect of Burnup and Holding Time of Irradiated Nuclear Fuel on the Mass Ratio of Am, Cm, Np, and Fissioning Plutonium

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Particulars of the Effect of the Internal Medium of a Fuel Element in High-Burnup Fuel on the Corrosion Cracking of Fuel-Element Cladding under Stress

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Recommendations for calculating the characteristics of thermal creep of mixed uranium–plutonium oxide fuel when analyzing fuel-element serviceability

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The development of an MCNP tally-based burnup code

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