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Homepage>BS Standards>27 ENERGY AND HEAT TRANSFER ENGINEERING>27.120 Nuclear energy engineering>27.120.30 Fissile materials>BS EN ISO 15366-1:2016 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 Samples containing plutonium in the microgram range and uranium in the milligram range
immediate downloadReleased: 2016-05-31
BS EN ISO 15366-1:2016 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 Samples containing plutonium in the microgram range and uranium in the milligram range

BS EN ISO 15366-1:2016

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 Samples containing plutonium in the microgram range and uranium in the milligram range

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Standard number:BS EN ISO 15366-1:2016
Pages:20
Released:2016-05-31
ISBN:978 0 580 90941 2
Status:Standard
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BS EN ISO 15366-1:2016


This standard BS EN ISO 15366-1:2016 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 is classified in these ICS categories:
  • 27.120.30 Fissile materials and nuclear fuel technology

This part of ISO 15366 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 (see ISO 8299[1]) or alpha spectrometry (see ISO 11483[2]).

This part of ISO 15366, 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.