Experiments performed at the Mayak Production Assiciation to determine the 232U content in spent BN-600 fuel are analyzed. Calculations show that to within the limits of error the concentration largely agrees with the measured value, which makes it possible to use the calculations for a preliminary assessment of the 232U content in batches of uranium regenerated from reprocessed spent BN-600 FA.

中文翻译：

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铀负载快反应堆废 FA 中 232U 含量的测定

分析了在 Mayak 生产协会进行的实验，以确定 BN-600 乏燃料中的 232U 含量。计算表明，在误差范围内，浓度与测量值基本一致，这使得可以使用计算结果对从再处理废 BN-600 FA 再生的铀批次中的 232U 含量进行初步评估。