Dec 3, 2024
8:00pm - 10:00pm
Hynes, Level 1, Hall A
Gabriel Murphy1,Sara Gilson2,Octavian Valu3,Olaf Walter3,Karin Popa3,Nina Huittinen4
Forschungszentrum Jülich GmbH1,Oak Ridge National Laboratory2,European Commission Joint Research Centre3,Helmholtz-Zentrum Dresden-Rossendorf4
Gabriel Murphy1,Sara Gilson2,Octavian Valu3,Olaf Walter3,Karin Popa3,Nina Huittinen4
Forschungszentrum Jülich GmbH1,Oak Ridge National Laboratory2,European Commission Joint Research Centre3,Helmholtz-Zentrum Dresden-Rossendorf4
The thermal and radiation stability of Zircaloy cladding material that houses spent nuclear fuel (SNF) is an important factor when considering the storage and eventual disposal of SNF in a geological repository. It is known that on the surface of the cladding, oxidised zirconia (ZrO<sub>2</sub>) phases are inherently present. Following fuel swelling and rim contact, the zirconia layer on the interior surface can interact with SNF elements, leading to the formation of phases such as pyrochlore and zirconates among others. These phases act as the first intermediate barrier between SNF and the metallic cladding and consequently are important to consider in safety design, particularly for release of radionuclides (RNs). A pertinent RN that contributes significantly to the radiological hazard of SNF, is the isotope Am-241. The chemistry of Am is largely unique, being able to readily dissociate between its tetravalent and trivalent states in oxides, making it difficult to investigate via surrogate studies. Furthermore, Am-241 has a relatively short t<sub>1/2</sub> of 432 years and decays via alpha emission (5.486 MeV), resulting in significant ensuing radiation damage in host materials. Consequentially, understanding the thermal and radiation stability of host material phases incorporating Am-241 is pertinent for safe disposal of SNF. As a part of the national project “AcE” funded by the German Federal Ministry of Education and Research (BMBF) and through the European Commission ActUsLab program, we have investigated several zirconium oxide polymorphs, including but not limited to Nd-pyrochlore and zirconia, doped with 5 mol% Am-241. The particular focus of the investigation is to understand the thermal and radiation stability of the different oxide polymorphs when Am-241 is incorporated. This presentation will highlight some on-going results from this research program including high-temperature phase transformations, radiation induced lattice swelling, phase separation, and associated apparent redox activity induced by the presence of Am-241. The experimental data used in this research were generated through access to the ActUsLab/FMR under the Framework of access to the Joint Research Centre Physical Research Infrastructures of the European Commission ( RISE-241, Research Infrastructure Access Agreement N°36344/02).