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>UNE standards>UNE 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 - Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range (ISO 15366-1:2014)
in stockReleased: 2016-09-28
UNE 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 - Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range (ISO 15366-1:2014)

UNE 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 - Part 1: Samples containing plutonium in the microgram range and uranium in the milligram range (ISO 15366-1:2014)

Tecnología de combustible nuclear. Separación y purificación química del uranio y el plutonio en soluciones de ácido nítrico para el análisis isotópico y de dilución isotópica mediante cromatografía de extracción por solventes. Parte 1: Muestras que contienen plutonio en el rango de microgramo y uranio en el rango de miligramo (ISO 15366-1: 2014)

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Standard number:UNE EN ISO 15366-1:2016
Pages:18
Released:2016-09-28
Status:Standard
DESCRIPTION

UNE EN ISO 15366-1:2016

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 ¼g to 150 ¼g 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.