Voloxidation of Mixed Nitride Uranium–Plutonium Spent Nuclear Fuel

نویسندگان

چکیده

Abstract The efficiency of voloxidation mixed nitride uranium–plutonium spent nuclear fuel (MNUP SNF) for the separation composition from rod cladding and removal 3 H 14 C was estimated. It shown that completeness SNF under optimal conditions is at level 98–99%. residual content tritium in voloxidized does not exceed 0.2% its original sample; radiocarbon removed by 98%.

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ژورنال

عنوان ژورنال: Radiochemistry

سال: 2023

ISSN: ['1066-3622', '1608-3288']

DOI: https://doi.org/10.1134/s1066362223020042