ISO 15366-1:2014 核燃料技術—溶媒抽出クロマトグラフィーによる同位体および同位体希釈分析のための硝酸溶液中のウランとプルトニウムの化学的分離と精製—パート1：マイクログラム範囲のプルトニウムとミリグラム範囲のウランを含むサンプル | ページ 2

Foreword

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The committee responsible for this document is ISO/TC 85, Nuclear energy, nuclear technologies, and radiological protection, Subcommittee SC 5, Nuclear fuel cycle.

This first edition, together with the first edition of ISO 15366-2, cancels and replaces the first edition of ISO 15366:1999, which has been technically revised.

ISO 15366 consists of the following parts, under the general title Chemical separation and purification of uranium and plutonium in nitric acid solutions for isotopic and isotopic dilution analysis by solvent extraction chromatography —

— Part 1: Sample containing plutonium in the microgram range and uranium in the milligram range

— Part 2: Sample containing plutonium and uranium amounts in the nanogram range and below

1 Scope

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.

Bibliography