BS EN ISO 15366-1:2016
Current
The latest, up-to-date edition.
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
Hardcopy , PDF
English
31-05-2016
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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
Explains 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.
| Committee |
NCE/9
|
| DevelopmentNote |
Renumbers and supersedes BS ISO 15366-1. 2016 version incorporates corrigendum to BS ISO 15366-1. Supersedes 11/30242060 DC. (05/2016)
|
| DocumentType |
Standard
|
| Pages |
20
|
| PublisherName |
British Standards Institution
|
| Status |
Current
|
| Supersedes |
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.
| Standards | Relationship |
| ISO 15366-1:2014 | Identical |
| EN ISO 15366-1:2016 | Identical |
| ISO 11483:2005 | Nuclear fuel technology — Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry |
| ISO 8299:2005 | Nuclear fuel technology Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry |
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