EN ISO 15366-1:2016

European foreword
Foreword
1 Scope
2 Principle of the method
3 Apparatus
4 Reagents
5 Procedure
6 Characteristics of the separation
7 Quality control
8 Interferences
Annex A (normative) - Packing and conditioning of the
        chromatographic columns as used in the ISO 15366-1
        procedure, loaded with an inert silica support coated
        with tri-n-octyl-phosphine-oxide (TOPO)
Bibliography

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.