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.

中文翻译：

---

测定废核燃料样品中of的比活度

摘要

制定了确定乏核燃料（SNF）样品中of比活度的程序，并进行了方法学认证。该程序用于确定在BOR-60和BN-600反应堆中辐照的混合氮化铀-p核燃料样品中of的比活度为8.5×10 ⁶ ±1.1×10 ⁵和2.6×10 ⁶ ±2.0× 10 ⁵ Bq / g。估算了在BN-600反应堆中辐照过的核燃料元件壳中的content含量，并评估了混合的氮化铀-p废核燃料中的oxid氧化过程去除removing的效率。