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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
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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

CURRENCY
LANGUAGE
English
Standard number:BS EN ISO 15366-1:2016
Pages:20
Released:2016-05-31
ISBN:978 0 580 90941 2
Status:Corrigendum
DESCRIPTION
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
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 ?g to 150 ?g 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.
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