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 $131.00
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
Language
English
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 10276:2019 Nuclear energy – Fuel technology – Trunnion systems for packages used to transport radioactive material
CDN $263.00 Add to cart -
ISO 12183:2024 Nuclear fuel technology – Controlled-potential coulometric measurement of plutonium
CDN $310.00 Add to cart -
ISO 16795:2024 Nuclear energy – Determination of Gd2O3 content in pellets containing uranium oxide by X-ray fluorescence spectrometry
CDN $131.00 Add to cart -
ISO 11483:2005 Nuclear fuel technology – Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry
CDN $195.00 Add to cart
