Thermal energy transport in oxide nuclear fuel
To efficiently capture the energy of the nuclear bond, advanced nuclear reactor concepts
seek solid fuels that must withstand unprecedented temperature and radiation extremes. In …
seek solid fuels that must withstand unprecedented temperature and radiation extremes. In …
Integrating advanced modeling and accelerated testing for a modernized fuel qualification paradigm
With the increasing interest in sodium fast reactor technology, as seen by applications to the
US Nuclear Regulatory Commission for the OKLO Aurora plant, fuel testing for the …
US Nuclear Regulatory Commission for the OKLO Aurora plant, fuel testing for the …
Combining mesoscale thermal transport and x-ray diffraction measurements to characterize early-stage evolution of irradiation-induced defects in ceramics
In situ characterization of defects, microstructure, and properties will provide new
perspectives regarding the structure-property relationship of materials in extreme …
perspectives regarding the structure-property relationship of materials in extreme …
Fuel performance design basis for the versatile test reactor
DL Porter, DC Crawford - Nuclear Science and Engineering, 2022 - Taylor & Francis
Abstract The Fuel Performance Design Basis for the Versatile Test Reactor begins with
requirements to maintain safe and efficient reactor operation. For the metal-fueled Versatile …
requirements to maintain safe and efficient reactor operation. For the metal-fueled Versatile …
Understanding the local thermal conductivity evolution of neutron irradiated U3Si2 dispersion fuel via state-of-the-art thermo-reflectance measurements
This study presents the first thermal conductivity measurements performed on neutron
irradiated U 3 Si 2 dispersion fuel cladded in an aluminum matrix (in a plate geometry) …
irradiated U 3 Si 2 dispersion fuel cladded in an aluminum matrix (in a plate geometry) …
Analysis of radially resolved thermal conductivity in high burnup mixed oxide fuel and comparison to thermal conductivity correlations implemented in fuel …
The thermal diffusivity and thermal conductivity of high burnup (19% FIMA) mixed oxide (U,
Pu) O 2 nuclear fuel has been measured along the radial direction using a …
Pu) O 2 nuclear fuel has been measured along the radial direction using a …
Post-irradiation examination of legacy high burnup fuel to support safety testing
F Cappia - 2021 - osti.gov
Safety/transient testing to evaluate performance under off-normal conditions is an essential
pillar for both the development of Accident Tolerant Fuels (ATF) and the optimization of fuel …
pillar for both the development of Accident Tolerant Fuels (ATF) and the optimization of fuel …