Voloxidation of Mixed Nitride Uranium–Plutonium Spent Nuclear Fuel

The efficiency of voloxidation of mixed nitride uranium–plutonium spent nuclear fuel (MNUP SNF) for the separation of the fuel composition from the fuel rod cladding and removal of 3 H and 14 C was estimated. It was shown that the completeness of SNF separation from fuel rod cladding under optimal c...

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Published inRadiochemistry (New York, N.Y.) Vol. 65; no. 2; pp. 177 - 184
Main Authors Momotov, V. N., Makarov, A. O., Volkov, A. Yu, Lakeev, P. V., Tikhonova, D. E., Dvoeglazov, K. N.
Format Journal Article
LanguageEnglish
Published Moscow Pleiades Publishing 01.04.2023
Springer Nature B.V
Subjects
Chemistry
Chemistry and Materials Science
Chemistry/Food Science
Cladding
Nitrides
Nuclear Chemistry
Nuclear fuel elements
Plutonium
Separation
Spent nuclear fuels
Tritium
Uranium
mixed nitride uranium–plutonium fuel
tritium
radiocarbon
fission products
radiochemical analysis
SNF voloxidation
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Summary:The efficiency of voloxidation of mixed nitride uranium–plutonium spent nuclear fuel (MNUP SNF) for the separation of the fuel composition from the fuel rod cladding and removal of 3 H and 14 C was estimated. It was shown that the completeness of SNF separation from fuel rod cladding under optimal conditions is at the level of 98–99%. The residual content of tritium in the voloxidized fuel does not exceed 0.2% of its content in the original SNF sample; radiocarbon is removed by 98%.
ISSN:1066-3622
1608-3288
DOI:10.1134/S1066362223020042