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Simulated Microstructural and Compositional Evolution of U-Pu-Zr Alloys Using the Potts-Phase Field Modeling Technique
- Source :
- Metallurgical and Materials Transactions A. 49:6457-6468
- Publication Year :
- 2018
- Publisher :
- Springer Science and Business Media LLC, 2018.
-
Abstract
- U-Pu-Zr alloys are considered ideal metallic fuels for experimental breeder reactors because of their superior material properties and potential for increased burnup performance. However, significant constituent redistribution has been observed in these alloys when irradiated, or subject to a thermal gradient, resulting in inhomogeneity of both composition and phase, which, in turn, alters the fuel performance. The hybrid Potts-phase field method is reformulated for ternary alloys in a thermal gradient and utilized to simulate and predict constituent redistribution and phase transformations in the U-Pu-Zr nuclear fuel system. Simulated evolution profiles for the U-16Pu-23Zr (at. pct) alloy show concentric zones that are compared with published experimental results; discrepancies in zone size are attributed to thermal profile differences and assumptions related to the diffusivity values used. Twenty-one alloys, over the entire ternary compositional spectrum, are also simulated to investigate the effects of alloy composition on constituent redistribution and phase transformations. The U-40Pu-20Zr (at. pct) alloy shows the most potential for compositional uniformity and phase homogeneity, throughout a thermal gradient, while remaining in the compositional range of feasible alloys.
- Subjects :
- Materials science
Metallurgy
Alloy
Metals and Alloys
Thermodynamics
02 engineering and technology
engineering.material
021001 nanoscience & nanotechnology
Condensed Matter Physics
Thermal diffusivity
01 natural sciences
010305 fluids & plasmas
Condensed Matter::Materials Science
Temperature gradient
Mechanics of Materials
0103 physical sciences
Homogeneity (physics)
Thermal
engineering
0210 nano-technology
Ternary operation
Material properties
Burnup
Subjects
Details
- ISSN :
- 15431940 and 10735623
- Volume :
- 49
- Database :
- OpenAIRE
- Journal :
- Metallurgical and Materials Transactions A
- Accession number :
- edsair.doi...........30afe68f7fce14fb9c06781f480248b7
- Full Text :
- https://doi.org/10.1007/s11661-018-4922-7