Heavy Minerals in Soils from the Athabasca Basin and the Implications for Exploration Geochemistry of Uranium Deposits at Depth

The Centennial deposit is a high grade (~8% U3O8), deeply buried (~950m), unconformity-related U deposit located in the south-central region of the Athabasca Basin in northern Saskatchewan, Canada. The mineral chemistry of fine fractions (<63 μm) of soils from grids above the Centennial deposit were examined to understand possible controls on the geochemistry and radiogenic 207Pb/206Pb ratios measured in the clay-size (<2 μm) fractions used for exploration. Soil samples distal and proximal to the deposit projection to the surface and geophysically defined structures were selected. Mineral abundances were determined using the scanning electron microscope and Mineral Liberation Analysis. Zircon was the only U-rich mineral identified with modal abundances >0.02% by weight. Monazite, which can be U-rich, was identified, but not in significant abundances. The source of the zircon and other heavy minerals is interpreted to be from sub-cropping sources that are >100 km up-ice from Centennial. Trace element analysis using laser ablation inductively coupled plasma mass spectrometry of hydroseparated zircon grains indicate that zircon abundances and zircon Pb concentrations in surficial samples have minimal effect on the radiogenic 207Pb/206Pb ratios in the clay-fraction of the samples, with the dominant source of radiogenic Pb being clay mineral surfaces that trapped Pb during secondary dispersion from the Centennial uranium deposit through faults and fractures to the surface. The REE patterns indicate HREE enrichment in the clay-fractions of samples that have higher abundances of zircon in the <20 μm fraction. Immobile elements such as HREE that are concentrated in zircon can be used as indicators of radiogenic Pb being sourced from minerals at the surface rather than being sourced from secondary dispersion from deeply buried U deposits.

THE MICROSTRUCTURES OF ZR-EXCEL ALLOY: EFFECTS OF HEAVY ION IRRADIATION, PLASTIC DEFORMATION, THERMAL TREATMENT AND IN-SITU HEATING

Zr-Excel alloy (Zr-3.5Sn-0.8Nb-0.8Mo) is a dual phase (α + β) alloy in the as-received pressure tube condition. It has been proposed to be the pressure tube candidate material for the Generation-IV CANDU-Supercritical Water Reactor (CANDU-SCWR). In this dissertation, the effects of heavy ion irradiation, deformation and heat treatment on the microstructures of the alloy were investigated to enable us to have a better understanding of the potential in-reactor performance of this alloy. In-situ heavy ion (1 MeV) irradiation was performed to study the nucleation and evolution of dislocation loops in both α- and β-Zr. Small and dense type dislocation loops form under irradiation between 80 and 450 °C. The number density tends to saturate at ~ 0.1 dpa. Compared with the α-Zr, the defect yield is much lower in β-Zr. The stabilities of the metastable phases (β-Zr and ω-Zr) and the thermal-dynamically equilibrium phase, fcc Zr(Mo, Nb)2, under irradiation were also studied at different temperatures. Chemi-STEM elemental mapping was carried out to study the elemental redistribution caused by irradiation. The stability of these phases and the elemental redistribution are strongly dependent on irradiation temperature. In-situ time-of-flight neutron diffraction tensile and compressive tests were carried out at different temperatures to monitor lattice strain evolutions of individual grain families during these tests. The β-Zr is the strengthening phase in this alloy in the as-received plate material. Load is transferred to the β-Zr after yielding of the α-Zr grains. The temperature dependence of static strain aging and the yielding sequence of the individual grain families were discussed. Strong tensile/compressive asymmetry was observed in the {0002} grain family at room temperature. The microstructures of the sample deformed at 400 °C and the samples only subjected to heat treatment at the same temperature were characterized with TEM. Concentration of β phase stabilizers in the β grain and the morphology of β grain have significant effect on the stability of β- and ω-Zr under thermal treatment. Applied stress/strain enhances the decomposition of isothermal ω phase but suppresses α precipitation inside the β grains at high temperature. An α → ω/ZrO phase transformation was observed in the thin foils of Zr-Excel alloy and pure Zr during in-situ heating at 700 °C in TEM.