Report on the Synchrotron Characterization of U-Mo and U-Zr Alloys and the Modeling Results
- Purdue Univ., West Lafayette, IN (United States)
- Illinois Inst. of Technology, Chicago, IL (United States)
- Brookhaven National Lab. (BNL), Upton, NY (United States)
ABSTRACT Uranium-molybdenum (U-Mo) and uranium-zirconium (U-Zr) are two promising fuel candidates for nuclear transmutation reactors which burn long-lived minor actinides and fission products within fast spectrum reactors. The objectives of this research are centered on understanding the early stages of fuel performance through the examination of the irradiation induced microstructural changes in U-Zr and U-Mo alloys subjected to low neutron fluences. Specimens that were analyzed include those that were previously irradiated in the Advanced Test Reactor at INL. This most recent work has focused on a sub-set of the irradiated specimens, specifically U-Zr and U-Mo alloys that were irradiated to 0.01 dpa at temperatures ranging from (150-800oC). These specimens were analyzed with two types of synchrotron techniques, including X-ray absorption fine structure and X-ray diffraction. These techniques provide non-destructive microstructural analysis, including phase identification and quantitation, lattice parameters, crystallite sizes, as well as bonding, structure, and chemistry. Preliminary research has shown changes in the phase fractions, crystallite sizes, and lattice parameters as a function of irradiation and temperature. Future data analyses will continue to explore these microstructural changes.
- Research Organization:
- Idaho National Laboratory (INL), Idaho Falls, ID (United States)
- Sponsoring Organization:
- USDOE Office of Nuclear Energy (NE)
- DOE Contract Number:
- AC07-05ID14517;
- OSTI ID:
- 1364512
- Report Number(s):
- INL/EXT--16-40130
- Country of Publication:
- United States
- Language:
- English
Similar Records
High Energy X-ray Applications for the Characterization of Metallic Uranium Alloys
Microstructure, Thermal, and Mechanical Properties Relationships in U and UZr Alloys (Final Report)
Interdiffusion between Zr Diffusion Barrier and U-Mo Alloy
Journal Article
·
Wed Jun 15 00:00:00 EDT 2016
· Transactions of the American Nuclear Society
·
OSTI ID:22992157
Microstructure, Thermal, and Mechanical Properties Relationships in U and UZr Alloys (Final Report)
Technical Report
·
Mon Jun 01 00:00:00 EDT 2020
·
OSTI ID:1632268
Interdiffusion between Zr Diffusion Barrier and U-Mo Alloy
Journal Article
·
Fri Nov 30 23:00:00 EST 2012
· Journal of Phase Equilibria and Diffusion
·
OSTI ID:1060421