Robert Aughterson
Profile Information
- Name
- Dr Robert Aughterson
- Institution
- ANSTO Nuclear Materials
- Position
- Experimental Physicist
- h-Index
- 25
- ORCID
- 0000-0002-1704-024X
- Expertise
- Ceramic Fuel, Crystallography, Glass-Ceramic Phase, Li-ion, Solid State Physics, X-Ray Diffraction (XRD)
Publications:
| "Atomic origins of radiation-induced defects and the role of lamellar interfaces in radiation damage of titanium aluminide alloy irradiated with Kr-ions at elevated temperature" Robert Aughterson, Hanliang Zhu, Meng Qin, Tao Wei, Gregory Lumpkin, Y Ma, Huijin Li, Acta Materialia Vol. 172 [unknown] 72-83 | ||
|
"Fabrication, crystal structure, and ion-irradiation response for Gd2(Ti1-xZrx)O5 (x = 0, 0.1, 0.2, 0.3, 0.4, 0.5) system"
Robert Aughterson, Wei-Ying Chen,
Journal of the American Ceramic Society
Vol.
2025
The development of radionuclide-containing matrixmaterials, for ceramic-based
high-level nuclear wasteforms or neutron absorbent fuel components, requires
both a robust matrix material and a neutron absorbent isotope. Here, we fabricated
a series of compounds Gd2(Ti1-xZrx)O5 (x = 0.0, 0.1, 0.2, 0.3, 0.4, 0.5) using
the conventional oxide route of mixing oxide precursors, pressing, and sintering
in air to various maximum temperatures. Crystal structure refinement of
x-ray diffraction data indicates zirconium-containing compounds to be of the
defect-fluorite form, Fm-3m space group. There is sequential decrease in the cell
parameter with increasing titanium content from Gd2Ti0.5Zr0.5O5, a = 5.27795
(4) Å to Gd2Ti0.8Zr0.2O5, a = 5.2475 (4) Å. However, electron diffraction analysis
highlights greater crystal structure complexity, including a 4× fluorite superstructure
and additional diffuse diffraction features. The Argonne National
Laboratory IVEM-Tandem in situ irradiation facility has been utilized to characterize
the 1 MeV krypton irradiation response for this system of compounds.
The addition of zirconium has improved the radiation response, increasing the
fluence required for amorphization and lowering the temperature for maintaining
the crystalline structure. For the Gd2Ti0.8Zr0.2O5, a critical temperature of
936 K was found, while for Gd2Ti0.5Zr0.5O5, the Tc was 565 K. |
Presentations:
| "Ion-irradiation resistance of Gd2TiO5 studied both via; bulk, ex-situ, and thin crystal, in-situ, TEM analysis" Robert Aughterson, The 3rd Workshope on TEM with In Situ Irradiation June 11-12, (2013) |
Accomplishments
NSUF Supported Research
NSUF Research Collaborations
Ion Irradiation tolerance of Gadolinium titanates / zirconates as candidates for waste form matrices - FY 2023 RTE 1st Call, #23-4529
Development of radiation tolerant matrices for rare-earths designed for burnable poisons as part of the nuclear fuel array - FY 2020 RTE 2nd Call, #20-4102
A study using stoichiometry to control structural disorder and subsequent radiation tolerance of rare-earth based zirconates and titanates - FY 2019 RTE 2nd Call, #19-1752