Reprocessability of molybdenum and magnesia based inert matrix fuels

• Authors: Elena L. Ebert , Andrey Bukaemskiy , Fabian Sadowski , Steve Lange , Andreas Wilden , Giuseppe Modolo
• Languages of publication: EN

Abstracts

EN

This work focuses on the reprocessability of metallic 92Mo and ceramic MgO, which is under investigation for (Pu,MA)-oxide (MA = minor actinide) fuel within a metallic 92Mo matrix (CERMET) and a ceramic MgO matrix (CERCER). Magnesium oxide and molybdenum reference samples have been fabricated by powder metallurgy. The dissolution of the matrices was studied as a function of HNO3 concentration (1-7 mol/L) and temperature (25-90°C). The rate of dissolution of magnesium oxide and metallic molybdenum increased with temperature. While the MgO rate was independent of the acid concentration (1-7 mol/L), the rate of dissolution of Mo increased with acid concentration. However, the dissolution of Mo at high temperatures and nitric acid concentrations was accompanied by precipitation of MoO3. The extraction of uranium, americium, and europium in the presence of macro amounts of Mo and Mg was studied by three different extraction agents: tri-n-butylphosphate (TBP), N,Nʹ-dimethyl-N,Nʹ-dioctylhexylethoxymalonamide (DMDOHEMA), and N,N,N’,N’- -tetraoctyldiglycolamide (TODGA). With TBP no extraction of Mo and Mg occurred. Both matrix materials are partly extracted by DMDOHEMA. Magnesium is not extracted by TODGA (D < 0.1), but a weak extraction of Mo is observed at low Mo concentration.

Keywords

EN

CERCER; CERMET; dissolution; inert matrix fuels (IMF); liquid-liquid extraction; minor actinides; reprocessing

• Publisher: De Gruyter Open
• Journal: Nukleonika
• Year: 2015
• Volume: 60
• Issue: 4
• Pages: 871-878

Dates

published

1 - 12 - 2015

accepted

15 - 9 - 2015

received

19 - 6 - 2015

online

30 - 12 - 2015

Contributors

author

Elena L. Ebert

• Institut für Energie- und Klimaforschung, Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Forschungszentrum Jülich GmbH (FZJ), 52425 Jülich, Germany, Tel.: [phone], Fax: [phone]

author

Andrey Bukaemskiy

• Institut für Energie- und Klimaforschung, Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Forschungszentrum Jülich GmbH (FZJ), 52425 Jülich, Germany, Tel.: [phone], Fax: [phone]

author

Fabian Sadowski

• Institut für Energie- und Klimaforschung, Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Forschungszentrum Jülich GmbH (FZJ), 52425 Jülich, Germany, Tel.: [phone], Fax: [phone]

author

Steve Lange

• Institut für Energie- und Klimaforschung, Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Forschungszentrum Jülich GmbH (FZJ), 52425 Jülich, Germany, Tel.: [phone], Fax: [phone]

author

Andreas Wilden

• Institut für Energie- und Klimaforschung, Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Forschungszentrum Jülich GmbH (FZJ), 52425 Jülich, Germany, Tel.: [phone], Fax: [phone]

author

Giuseppe Modolo

• Institut für Energie- und Klimaforschung, Nukleare Entsorgung und Reaktorsicherheit (IEK-6), Forschungszentrum Jülich GmbH (FZJ), 52425 Jülich, Germany, Tel.: [phone], Fax: [phone]

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Identifiers

DOI

10.1515/nuka-2015-0124