Diploma & Master thesis projects


Interaction of Eu3+ and Cm3+ with Zircaloy and its corrosion product ZrO2

Master student:
Lucas Opitz
Supervisors:
Dr. Nina Huittinen, Prof. Thorsten Stumpf (HZDR)
Departement:
Surface processes
Period:
05/2021 – 20/2021

ZrO2 is a very interesting matrix regarding the interaction of spent nuclear fuel with technical barriers in the case of water ingress. Zircaloy, an alloy based on mostly Zirconium, is used as cladding material for fuel rods and will therefore be one of the first technical barriers when it comes to immobilization of radiotoxic nuclides such as minor actinides like Pu and Cm for example. During the operation in a nuclear power plant the alloy forms an oxide layer on the surface, ZrO2. My goal is to study the interaction of Eu3+ and Cm3+ as representatives for Lanthanides and Actinides in the oxidation state +3 since they have great luminescence properties with Zirconium(IV)-oxide. Former Ph.D. student Manuel Eibl investigated different concentration effects on the crystal structure of ZrO2. I want to simulate repository conditions to my samples by treating them at slightly elevated temperatures over a long period of time. Also I want to analyze the mechanism of the incorporation by various experiments. Finally I want to apply the same experimental conditions to the actual material Zircaloy to see if the results from the pure ZrO2 experiments match the final application.