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Repartition of the uranium isotopes within the Belgian UOX spent fuel

Published online by Cambridge University Press:  16 February 2017

Th. Mennecart ,
C. Cachoir ,
K. Lemmens ,
K. Govers ,
A. Dobney  and
L. Adriaensen
Th. Mennecart*
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
C. Cachoir
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
K. Lemmens
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
K. Govers
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
A. Dobney
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
L. Adriaensen
Affiliation:
SCK•CEN, Boeretang 200, B-2400 Mol, Belgium
*
*(Email: thierry.mennecart@sckcen.be)
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Abstract

In the framework of the Euratom FIRST-Nuclides program, SCK•CEN conducted leaching experiments on a PWR UOX fuel, taken from the Belgian Tihange 1 reactor, with an average rod burnup of 50 MWd/kgHM in order to determine the rapid release of some of the most critical radionuclides. Experiments were conducted with an intact and a declad spent fuel segment in contact with a reference carbonate solution. During one year, samplings were performed to determine the release of the most relevant radionuclides. The samples taken after six months of leaching were analysed by means of Thermal Ionisation Mass Spectrometry (TIMS). These results were compared to the total inventory measured with radiochemical burnup analyses, as well as with the calculated inventory profile along the pellet radius. The comparison gives information about the origin of the dissolved uranium.

Keywords

oxideUcorrosion
Type
Articles
Information
MRS Advances , Volume 1 , Issue 62: Scientific Basis for Nuclear Waste Management XXXIX , 2016 , pp. 4139 - 4145
Copyright
Copyright © Materials Research Society 2017 

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References

REFERENCES

Mennecart, T., Lemmens, K., Cachoir, C., Adriaensen, L. and Dobney, A.. Leaching test for the experimental determination of IRF radionuclides from Belgian high burnup spent nuclear fuel in First-Nuclides. Antwerp, Belgium (2013).Google Scholar
Govers, K., Verwerft, M., Van Renterghem, W., Lemmens, K., Mennecart, T., Cachoir, C., Adriaensen, L., Dobney, A. and Gysemans, M.. Characterization of SCK•CEN fuel samples used for leach tests in FIRST-NUCLIDES. Oral Presentation First Nuclides international Workshop (2013).Google Scholar
ORNL. (2011). Scale: A Comprehensive Modeling and Simulation Suite for Nuclear Safety Analysis and Design. ORNL/TM-2005/39, Version 6.1, June 2011.Google Scholar
Serrano-Purroy, D., Casis, I., Gonzalez-Robles, E., Glatz, J.P., Wegen, D.H., Clarens, F., Giménez, J., De Pablo, J. and Martinez-Esparza, A., Dynamic leaching studies of 45 MWd/kgU UO2 commercial spent nuclear fuel under oxic conditions, J. Nucl. Mat. 434, 451 (2013).Google Scholar