Abstract
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 8.5×106 ± 1.1×105 and 2.6×106 ± 2.0×105 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.
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