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Simfuel Leaching Studies in Granitic Groundwater Under Oxidizing Conditions

Published online by Cambridge University Press:  15 February 2011

J. Garcia-Serrano ,
J. A. Serrano ,
P. P. Diaz-Arocas ,
J. Quiñones  and
J. L. R. Almazan
J. Garcia-Serrano
Affiliation:
CIEMAT-ITN. Avda. Complutense, 22. 28040 Madrid (Spain)
J. A. Serrano
Affiliation:
CIEMAT-ITN. Avda. Complutense, 22. 28040 Madrid (Spain)
P. P. Diaz-Arocas
Affiliation:
CIEMAT-ITN. Avda. Complutense, 22. 28040 Madrid (Spain)
J. Quiñones
Affiliation:
CIEMAT-ITN. Avda. Complutense, 22. 28040 Madrid (Spain)
J. L. R. Almazan
Affiliation:
CIEMAT-ITN. Avda. Complutense, 22. 28040 Madrid (Spain)
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Abstract

Simulated high-bumup nuclear fuel (SIMFUEL) has been leached in synthetic groundwater under oxic conditions. SIMFUEL pellets were ground and sieved to two particle sizes (50–100 and 100–315 μm). An extensive solid characterization of the fragments was carried out by various techniques. Elemental analysis has also been performed prior to the leaching tests.

The release of U and the minor components (Mo, Ba and Sr) was monitored during the long term dissolution experiments (350 days). These minor components exhibit a trend similar to uranium, high release at the beginning followed by a plateau. The M/U calculated ratios show different behavior although after a period of time, depending on the particle sizes, constant ratios were observed.

SIMHUEL powder was used in order to simulate the physical effect of bum-up on the fuel structure. This fact seems to play an important role on the uranium release. A comparison with the results given in the literature for SIMFUEL pellet leaching tests shows good agreement with the values reported.

Type
Research Article
Information
MRS Online Proceedings Library (OPL) , Volume 412: Symposium V – Scientific Basis for Nuclear Waste Management XIX , 1995 , 83
Copyright
Copyright © Materials Research Society 1996

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