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Title: Thermomechanical Process Optimization of U-10wt% Mo – Part 1: High-Temperature Compressive Properties and Microstructure

Nuclear power research facilities require alternatives to existing highly enriched uranium alloy fuel. One option for a high density metal fuel is uranium alloyed with 10wt% molybdenum (U-10Mo). Fuel fabrication process development requires specific mechanical property data that, to-date, has been unavailable. In this work, as-cast samples were compression tested at three strain rates over a temperature range of 400 to 800° C to provide data for hot rolling and extrusion modeling. The results indicate that with increasing test temperature the U-10Mo flow stress decreases and becomes more sensitive to strain rate. In addition, above the eutectoid transformation temperature, the drop in material flow stress is prominent and shows a strain-softening behavior, especially at lower strain rates. Room temperature X-ray diffraction (XRD), scanning electron microscopy (SEM) combined with electron dispersive spectroscopy (EDS) analysis of the as-cast and compression tested samples were conducted. The analysis revealed that the as-cast and the samples tested below the eutectoid transformation temperature were predominantly γ phase with varying concentration of molybdenum whereas the ones tested above the eutectoid transformation temperature underwent significant homogenization.
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Publication Date:
OSTI Identifier:
Report Number(s):
Journal ID: ISSN 0022-3115; NN9100000
DOE Contract Number:
Resource Type:
Journal Article
Resource Relation:
Journal Name: Journal of Nuclear Materials; Journal Volume: 465
Research Org:
Pacific Northwest National Laboratory (PNNL), Richland, WA (US)
Sponsoring Org:
Country of Publication:
United States
U-10wt%Mo, Mechanical Properties, Microstructure, Compression Testing