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Determination of solubility in nitric acid of plutonium in unirradiated mixed oxide fuel pellets (U, Pu) O2. | Status: Current
description
1 Scope
This International Standard specifies an analytical method for determining the solubility in nitric acid of plutonium in pellets of unirradiated mixed oxide fuel (light-water reactor fuels). The results provide information about the expected dissolution behaviour of irradiated pellets under industrial reprocessing conditions. In this aspect, the specific conditions (e.g. time of the test) may vary depending upon the need to match to a specific reprocessor’s requirements. The test is aimed at determining solubility under equilibrium conditions rather than the kinetics of dissolution and hence allows for a second dissolution period.
Details
Publisher
BS
File size
708.66 KB
Pages
12
Format
PDF
Publication date
2018-01-18
ISBN-13
978-0-580-96936-2
ISBN-13 plain
9780580969362
ISBN-10
0580969362