ISO 24459:2021
ISO 24459:2021 Determination of uranium content in samples coming from the nuclear fuel cycle by L-absorption edge spectrometry
CDN $193.00
Description
This document specifies a method for the determination of uranium concentrations in nitric acid or TBP-DILUANT (for example TBP-kerosene) solutions coming from the nuclear fuel cycle.
The method is applicable
-    for process control of solutions, free of suspension, which contain between 10 g/l to 300 g/l uranium, and
-    for high accuracy purposes (Safeguards) to nitric acid solutions, free of suspension, which contain between 100 g/l and 220 g/l uranium.
Having
-    the content of neptunium and plutonium impurities in the solution less than 1 % of the uranium content.
-    the content of neutron poisons (gadolinium, erbium) less than 1 % of the uranium content to ensure the absence of significant interferences at the level of required precision, for high accuracy purposes.
The method is applicable to solid samples as well, provided that they can be fully dissolved in nitric acid.
Edition
1
Published Date
2021-10-06
Status
PUBLISHED
Pages
13
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
This document specifies a method for the determination of uranium concentrations in nitric acid or TBP-DILUANT (for example TBP-kerosene) solutions coming from the nuclear fuel cycle.
The method is applicable
-    for process control of solutions, free of suspension, which contain between 10 g/l to 300 g/l uranium, and
-    for high accuracy purposes (Safeguards) to nitric acid solutions, free of suspension, which contain between 100 g/l and 220 g/l uranium.
Having
-    the content of neptunium and plutonium impurities in the solution less than 1 % of the uranium content.
-    the content of neutron poisons (gadolinium, erbium) less than 1 % of the uranium content to ensure the absence of significant interferences at the level of required precision, for high accuracy purposes.
The method is applicable to solid samples as well, provided that they can be fully dissolved in nitric acid.
Previous Editions
Can’t find what you are looking for?
Please contact us at:
Related Documents
-
ISO 18557:2017 Characterisation principles for soils, buildings and infrastructures contaminated by radionuclides for remediation purposes
CDN $349.00 Add to cart -
ISO 11483:2005 Nuclear fuel technology – Preparation of plutonium sources and determination of 238Pu/239Pu isotope ratio by alpha spectrometry
CDN $193.00 Add to cart -
ISO 13464:1998 Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants – Combined method using K-absorption edge and X-ray fluorescence spectrometry
CDN $193.00 Add to cart -
ISO 22765:2025 Nuclear fuel technology – Sintered (U,Pu)O2 pellets – Guidance for ceramographic preparation for microstructure examination
CDN $130.00 Add to cart
