
ISO 15366:2014
ISO 15366:2014 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
CDN $115.00
Description
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 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.
Edition
1
Published Date
2014-06-17
Status
PUBLISHED
Pages
10
Format 
Secure PDF
Secure – PDF details
- Save your file locally or view it via a web viewer
- Viewing permissions are restricted exclusively to the purchaser
- Device limits - 3
- Printing – Enabled only to print (1) copy
See more about our Environmental Commitment
Abstract
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 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.
Previous Editions
Can’t find what you are looking for?
Please contact us at:
Related Documents
-

ISO 18256:2019 Nuclear fuel technology – Dissolution of plutonium dioxide-containing materials – Part 2: Dissolution of MOX pellets and powders
CDN $115.00 Add to cart -

ISO 18213:2009 Nuclear fuel technology – Tank calibration and volume determination for nuclear materials accountancy – Part 3: Statistical methods
CDN $312.00 Add to cart -

ISO 16966:2013 Nuclear energy – Nuclear fuel technology – Theoretical activation calculation method to evaluate the radioactivity of activated waste generated at nuclear reactors
CDN $312.00 Add to cart -

ISO 10276:2019 Nuclear energy – Fuel technology – Trunnion systems for packages used to transport radioactive material
CDN $233.00 Add to cart







