ISO 7097-2:2004 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 7097-2:2004
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：2004-07
标准范围
ISO 7097:第2部分描述了测定核燃料循环中纯产品材料样品（如金属铀、UO2、UO3、六水合硝酸铀酰、六氟化铀和U3O8）中铀的分析方法。该程序足够准确和精确，可用于核材料清点。该方法不会像重铬酸钾滴定那样产生有毒的混合废物。在通过获得与重铬酸钾法在相同样品类型上获得的结果在统计学上等同的结果进行鉴定之前，该方法不得应用于废料或废弃样品。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。这并不排除使用可以提供等效性能的任何替代技术。由于该方法的一些步骤的性能是关键的，使用一些自动装置具有一些优点，主要是在常规分析的情况下。
ISO 7097:Part 2 describes an analytical method for the determination of uranium in pure product material samples such as U metal, UO2, UO3, uranyl nitrate hexahydrate, uranium hexafluoride and U3O8 from the nuclear fuel cycle. This procedure is sufficiently accurate and precise to be used for nuclear materials accountability.This method does not generate a toxic mixed waste as does the potassium dichromate titration. The method may not be applied to scrap or waste samples until such time as it is qualified by obtaining results statistically equivalent to those obtained by the potassium dichromate method on the same sample types.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 any alternative techniques which could give equivalent performance. As the performance of some steps of the method is critical, the use of some automatic device has some advantages, mainly in the case of routine analysis.
标准预览图
