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Design of a New Reactor to Work at Low Volume Liquid/Surface Solid Ratio and High Pressure and Temperature: Dissolution Rate Studies of UO2 Under Both Anoxic and Reducing Conditions.

Published online by Cambridge University Press:  01 July 2014

A. Martínez-Torrents ,
J. Giménez ,
I. Casas  and
J. de Pablo
A. Martínez-Torrents
Affiliation:
CTM Centre Tecnològic, Plaça de la ciència 2, 08243 Manresa, Spain Departament of Chemical Engineering, Universitat Politècnica de Catalunya, Diagonal 647 H-4, 08028 Barcelona, Spain.
J. Giménez
Affiliation:
Departament of Chemical Engineering, Universitat Politècnica de Catalunya, Diagonal 647 H-4, 08028 Barcelona, Spain.
I. Casas
Affiliation:
Departament of Chemical Engineering, Universitat Politècnica de Catalunya, Diagonal 647 H-4, 08028 Barcelona, Spain.
J. de Pablo
Affiliation:
CTM Centre Tecnològic, Plaça de la ciència 2, 08243 Manresa, Spain Departament of Chemical Engineering, Universitat Politècnica de Catalunya, Diagonal 647 H-4, 08028 Barcelona, Spain.
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Abstract

A flow-through experimental reactor has been designed in order to perform studies at both high pressure and high temperature conditions. A chromatographic pump is used to impulse the leachant throughout the reactor in order to work at very low flows but high pressures. Therefore, high surface solid to volume leachant ratios, similar to the ones predicted in the final repository, can be obtained. The reactor allows working at different atmospheres at pressures up to 50 bars. The temperature inside the reactor can be set using a jacket.

Using this new reactor the evolution of uranium concentrations released from an UO2 sample was studied at different conditions.

The results show that at hydrogen pressures between 5 and 7 bars, hydrogen peroxide does not seem to significantly oxidize the uranium (IV) oxide. Uranium concentrations in those experiments remain between 10-8 mol·l-1 and 10-9 mol·l-1.

Keywords

Ukineticsoxidation
Type
Articles
Information
MRS Online Proceedings Library (OPL) , Volume 1665: Symposium NW – Scientific Basis for Nuclear Waste Management XXXVII , 2014 , pp. 303 - 309
Copyright
Copyright © Materials Research Society 2014 

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