J. Giglio

Effect of Process Variables During the Head-End Treatment of Spent Oxide Fuel

B. Westphal, R. Lind, D. Cummings, 2006 .

Post-Irradiation Characterization of a high burnup Mixed Oxide Fuel Rod with Minor Actinides

K. Mcclellan, P. Medvedev, P. Hosemann, 2022, Journal of Nuclear Materials.

Measurements of effective actinides neutron capture cross sections in a cadmium-filtered epithermal neutron spectrum

D. Clark, G. Youinou, G. Palmiotti, 2021 .

Elevated temperature microcantilever testing of fresh U-10Mo fuel

P. Hosemann, D. Frazer, D. Jädernäs, 2019 .

Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements

F. Cappia, S. Middlemas, J. Cole, 2021, Journal of Nuclear Materials.

Annealing influence on the microstructure of irradiated U-Mo monolithic fuel foils

T. Trowbridge, J. Cole, J. Jue, 2023, Nuclear Materials and Energy.

Impacts of annealing treatment on the microstructure of U-Mo monolithic fuel plates

J. Cole, J. Jue, J. Giglio, 2022, Journal of Nuclear Materials.