ISO 7097-2:2022 核燃料技术 在溶液、六氟化物和固体中铀的测定-第1部分： 还原铁 （IV ） /氧化铈滴定法
标准编号：ISO 7097-2:2022
中文名称：核燃料技术 在溶液、六氟化物和固体中铀的测定-第1部分： 还原铁 （IV ） /氧化铈滴定法
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
发布日期：2022-11
标准范围
本文件描述了一种测定纯产品材料样品中铀的分析方法，如U？来自核燃料循环的金属、UO2、UO3、U3O8、六水合硝酸铀酰和六氟化铀。该程序足够准确和精确，可用于核材料清点。该方法可直接用于大多数经辐照或未辐照的铀和氧化铀核反应堆燃料以及硝酸铀产品溶液的分析。裂变产物相当于高达10？重原子的%燃耗不会干扰，并且可能引起干扰的其他元素通常不会以足够的量存在以显著影响结果。该方法建议称重一份样品并使用质量滴定，以提高精密度和准确度。这并不排除使用可提供等效性能的替代技术。在方法的一些关键步骤的执行中使用自动装置具有一些优点，主要是在常规分析的情况下。该方法不会像ISO中的重铬酸钾滴定那样产生有毒的混合废物？7097-1.
This document describes an analytical method for the determination of uranium in samples from pure product materials such as U metal, UO2, UO3, U3O8, 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.
标准预览图
