ISO 7097-1:2004 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 （II ） /氧化重铬酸钾盐滴定法
标准编号：ISO 7097-1:2004
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 （II ） /氧化重铬酸钾盐滴定法
英文名称：Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method
发布日期：2004-07
标准范围
ISO 7097-1:20 04描述了一种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。相当于高达10%的重原子燃耗的裂变产物不会产生干扰，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 7097-1:2004 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 can be used directly for the analysis of most uranium and uranium oxide nuclear reactor fuels, either irradiated or unirradiated, 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 any alternative technique 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
