Determining the Specific Activity of Tritium in Samples of Spent Nuclear Fuel

Determining the Specific Activity of Tritium in Samples of Spent Nuclear Fuel

Procedure for determining the specific activity of tritium in samples of spent nuclear fuel (SNF) was developed and methodologically certified. The procedure was used to determine the specific activity of tritium in samples of mixed nitride uranium-plutonium nuclear fuel irradiated in BOR-60 and BN-...

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Veröffentlicht in:Radiochemistry (New York, N.Y.) N.Y.), 2021, Vol.63 (1), p.66-71
Hauptverfasser: Momotov, V. N., Erin, E. A., Volkov, A.Yu, Tikhonova, D. E., Kupriyanov, A. S.
Format: Artikel
Sprache:eng
Schlagworte:
Chemistry
Chemistry and Materials Science
Chemistry/Food Science
Nitrides
Nuclear Chemistry
Nuclear fuel elements
Nuclear fuels
Nuclear reactors
Plutonium
Radioactive wastes
Spent nuclear fuels
Tritium
Uranium
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Zusammenfassung:Procedure for determining the specific activity of tritium in samples of spent nuclear fuel (SNF) was developed and methodologically certified. The procedure was used to determine the specific activity of tritium in samples of mixed nitride uranium-plutonium nuclear fuel irradiated in BOR-60 and BN-600 reactors to be 8.5×10 6 ± 1.1×10 5 and 2.6×10 6 ± 2.0×10 5 Bq/g, respectively. The content of tritium in the shell of a nuclear fuel element irradiated in a BN-600 reactor was estimated, and the efficiency of the voloxidation procedure of the mixed nitride uranium-plutonium spent nuclear fuel for removing tritium was evaluated.
ISSN:1066-3622
1608-3288
DOI:10.1134/S1066362221010100