NSUF - Nuclear Science User Facilities

Correlating microstructure to the thermal conductivity of irradiated U-20Pu-10Zr fuels

Full Details
Principal Investigator
Name:
Allison Probert
Email:
[email protected]
Phone:
(208) 526-6918
Team Members:
Name: Institution: Expertise: Status:
Assel Aitkaliyeva University of Florida Advanced Fuels, Electron Microscopy, In Situ Irradiations, Ion Beam Irradiation, Mechanical Behavior of Materials, Mechanical Properties, Mechanical Testing, microstructure characterization, Microstructure-Property Relationship, Nuclear Fuel Faculty
Cynthia Adkins Idaho National Laboratory Austenitic, Characterization, Iron Based Alloy, Martensite Steel, Microscopy, plutonium compounds, Stainless Steel, Thermal Conductivity, thermal diffusivity, thermal expansion, Thermophysical Properties, uranium compounds, Uranium Zirconium Other
Luca Capriotti Idaho National Laboratory Fast Reactor, Fast reactor MOX fuel, Fuel cladding chemical interaction (FCCI), HT9, Irradiated Fuels, Metal Fuels, Oxide Fuels, PIE Other
Experiment Details:
Experiment Title:
Correlating microstructure to the thermal conductivity of irradiated U-20Pu-10Zr fuels )
Work Description:
We will leverage microstructural information collected as part of NSUF project 18-14704, which consists of optical and scanning electron microscopy (OM/SEM), electron probe microanalysis (EPMA) to obtain chemical compositions of the phases and transmission electron microscopy-based (TEM) selective area electron diffraction (SAED) analysis to obtain crystallographic information for each phase. The fuel examined using these techniques is now available to the PIs for thermal conductivity measurements. This sample will be examined using thermo-reflectance methods, which co-PI Adkins has set up for use on irradiated fuels. The locations where thermal conductivity will be measured will be marked using fiducial markings in a Plasma Focused Ion Beam (PFIB) instrument. The locations will be approximately 100-200 μm apart starting from the center of the fuel pin and extending on the radius of the sample. Since this fuel has been examined in the past, we will correlate TCM measurement locations with TEM lift-out locations.
Abstract
The objective of the proposed work is to measure the local thermal conductivity of U-Pu-Zr fuel irradiated to 11 at. % burnup using thermo-reflectance methods in the thermal conductivity microscope (TCM). The collected thermal conductivity data will be correlated to the microstructure and the phases present in each constituent redistribution region. The microstructural characterization data has been previously collected and analyzed as part of NSUF project. The focus of this project is the measurements of thermal conductivity of U-20Pu-10Zr fuel. This work will enhance the understanding of the thermal behavior of U-Pu-Zr alloy and advance the development of fuel performance code for metallic fuels.

About Us

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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