标准摘要
[中文适用范围]: 本文件介绍了一种用于测定核燃料循环中纯产品材料样品(例如铀金属、二氧化铀、三氧化二铀、八氧化三铀、六水合硝酸铀酰和六氟化铀)中铀含量的分析方法。该程序足够准确和精确,可用于核材料责任追究。该方法可直接用于分析大多数铀和氧化铀核反应堆燃料(无论是辐照的还是未辐照的),以及硝酸铀产品溶液。相当于重原子燃耗 10% 的裂变产物不会造成干扰,而可能造成干扰的其他元素的数量通常不足以对结果产生显著影响。 [外文原描述]: This document describes an analytical method for the determination of uranium in samples from pure product materials such as U metal, UO 2 , UO 3 , U 3 O 8 , uranyl nitrate hexahydrate and uranium hexafluoride from the nuclear fuel cycle. This procedure is sufficiently accurate and precise to be used for nuclear materials accountability. This method can be used directly for the analysis of most uranium and uranium oxide nuclear reactor fuels, either irradiated or un-irradiated, and of uranium nitrate product solutions. Fission products equivalent to up to 10 % burn-up of heavy atoms do not interfere, and other elements which could cause interference are not normally present in sufficient quantity to affect the result significantly. The method recommends that an aliquot of sample is weighed and that a mass titration is used, in order to obtain improved precision and accuracy. This does not preclude the use of alternative techniques which could give equivalent performance. The use of automatic device(s) in the performance of some critical steps of the method has some advantages, mainly in the case of routine analysis. This method does not generate a toxic mixed waste as does the potassium dichromate titration in ISO 7097 - 1 .
英文名称Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method