Nuclear fuel technology — Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography — Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range
核燃料技术 - 通过溶剂萃取色谱法对硝酸溶液中的铀和钚进行同位素和同位素稀释分析的化学分离和纯化 - 第1部分:在毫微米范围内的微量范围和铀中含有钚的样品
发布日期:
2014-06-17
ISO 15366-1:20 14描述了在通过例如质谱法或α光谱法进行同位素分析之前,对辐照轻水反应堆燃料的溶解溶液和乏燃料后处理厂的高活性液体废物样品中的铀和钚进行化学分离和纯化的程序。ISO 15366-1:20 14描述了一种基于色谱法分离乏燃料类型样品中铀和钚的技术。该程序适用于在最多2 ml的3 mol·l-1硝酸溶液中含有1 μ g至150 μ g Pu(IV)和(VI)以及0.1 mg至2 mg U(IV)和(VI)的样品。它适用于铀和钚的混合物,其中铀/钚比的范围为0至200。
ISO 15366-1:2014 describes procedures to chemically separate and purify uranium and plutonium in dissolved solutions of irradiated light water reactor fuels and in samples of high active liquid waste of spent fuel reprocessing plants, prior to their isotopic analysis by e.g. mass spectrometric method or alpha spectrometry. ISO 15366-1:2014 describes a technique for the separation of uranium and plutonium in spent fuel type samples based on chromatographic method. The procedure applies to samples containing 1 μg to 150 μg Pu (IV) and (VI) and 0,1 mg to 2 mg U (IV) and (VI) in up to 2 ml of 3 mol·l-1 nitric acid solution. It is applicable to mixtures of uranium and plutonium in which the U/Pu-ratio can range from 0 up to 200.