"Analysis of radially resolved thermal conductivity in high burnup mixed oxide fuel and comparison to thermal conductivity correlations implemented in fuel performance codes" Marat Khafizov, Joshua Ferrigno, Tsvetoslav Pavlov, Narayan Poudel, Daniele Salvato, Chuting Tan, Troy Munro, Fabiola Cappia, Journal of Nuclear Materials Vol. 596 2024 Link | ||
"Impact of neutron irradiation on the thermophysical properties of additively manufactured stainless steel and inconel" Mark Graham, Jeffrey King, Tsvetoslav Pavlov, Cynthia Adkins, Scott Middlemas, Donna Guillen, Journal of Nuclear Materials Vol. 549 2021 Link |
Thermal Diffusivity Characterization of Irradiated Minor Actinide-Bearing Metal Fuel Pin G591 from the EBR-II X501 Experiment - FY 2025 RTE 1st Call, #25-5241
Spatially resolved thermal conductivity measurement of medium burnup MOX fuel - FY 2023 RTE 1st Call, #23-4587
Assessing the Radial Thermal Conductivity Change in FBR MOX Fuel - FY 2021 RTE 1st Call, #21-4304
Local thermal properties of fast reactor MOX fuels - FY 2021 RTE 1st Call, #21-4263
The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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