A procedure has been developed for the determination of ²³²U and ²³⁶Pu content by alpha spectrometry by ion-exchange isolation and purification of uranium and plutonium fractions from irradiated fuel solution. The proposed procedure has been utilized to determine weight concentrations of ²³²U and ²³⁶Pu in samples of uranium oxide fuel irradiated in VVER-1000 and RBMK-1000 reactors, as well as in mixed uranium-plutonium nitride fuel irradiated in a BN-600 reactor.

中文翻译：

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废核燃料232 U和236 Pu重量含量的测定

已经开发出一种通过α光谱法，通过离子交换分离和从辐照燃料溶液中纯化铀和p馏分来测定²³² U和²³⁶ Pu含量的方法。拟议的程序已用于确定VVER-1000和RBMK-1000反应堆中辐照的铀氧化物燃料样品以及BN-600反应堆中辐照的铀-氮化nitride混合燃料样品中²³² U和²³⁶ Pu的重量浓度。