Single Molecule Observations of Desorption-Mediated Diffusion at the Solid-Liquid Interface
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Elevated uranium concentrations in groundwater remain a persistent challenge at contaminated sites. Several sites rely on natural flushing of uranium as a remediation strategy. Uncertainties in conceptual models can cause remediation strategies to underestimate timeframes required to reach remediation goals. In this study, laboratory experiments were conducted to investigate uranium flushing of sediments from a site with persistent groundwater contamination. Six columns were used to simulate alkalinity-enhanced flushing of uranium from sediments, by switching influent alkalinity after ~12 pore volumes. About 20% to 31% of sediment uranium was consistently flushed from the sediments. K d values varied greatly (5.3 to 117 L/kg) but were consistently lower (20% to 50%) during influents with elevated alkalinity. The mass of uranium recovered from the columns also was consistently higher (5% to 80%) during alkalinity-enhanced flushing periods. However, column experiments with sequentially increasing alkalinity showed diminishing returns in uranium elution at higher carbonate concentrations. The loss of flushing efficiency is attributed to significant calcite precipitation at higher alkalinities. Furthermore, the results show that alkalinity-enhanced flushing of uranium could be employed as a viable remediation scheme if calcite precipitation could be minimized in a field application.
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The equipment and method for and results of calibration of the Sandia/CA TDS system for hydrogen quantification is presented. This technique for calibration can be used to quantify the hydrogen content titanium subhydride, titanium hydride, and any other hydrogen-containing material that desorbs its hydrogen in the form of molecular hydrogen below 1450°C.
Abstract not provided
Two decimeter-scale 2D experiments were conducted in the proposed research. To the extent possible, the first experiment (2.44 m x 0.61 m x 10 cm) was be packed to reproduce the observed distributions of sediment size fractions in the subsurface at the tracer test site. Four size fractions of sediment (<125m, 125-250m, 250m to 2 mm, >2mm) were packed in the tank and the size fractions were placed in a sediment structure imitating pattern rather than the block pattern used in the previous experiments conducted with Naturita sediment. The second tank used the same total amount of sediment and proportions of the three size fractions used in the first experiment but was packed at larger geostatistical correlation lengths to evaluate how the scale of heterogeneity affects the upscaling results. This experiment was conducted with the goal of trying to determine how the upscaling would be affected by the diffusion path length associated with low permeability zones. The initial conditions in the tanks were based on observed field conditions. The influent was a synthetic groundwater that mimicked uncontaminated groundwater observed at the Naturita site. Samples were collected from side and end ports of the tank and were analyzed for U(VI), alkalinity, pH and major ions as was done in previous experiments. Each decimeter scale experiment was run for approximately 6 months and the experiments were run in parallel. Extensive premodeling occurred for both tanks and lasted the first year of the project.
This progress report (M4FT-14LL0807031) describes research conducted at LLNL as part of the Crystalline Repository effort within the UFD program. Part I describes the dissolution kinetics of intrinsic Pu colloids synthesized in an alkaline solution. Part II describes the morphology and dissolution characteristics of various forms of Pu oxides prepared over a range of solution and temperature conditions. Proposed FY15 activities are identified.
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Previous experiments utilizing the planar MITL foil platform (T.J. Smith et al. RSI 2021) on the 1-MA, 100-ns Mykonos facility have shown neutral atomic and molecular hydrogen in the gap after rapid heating of the foil surfaces before breakdown. Additionally, previous attempts at using parylene-N as a coating for power flow surfaces on the 1-MA, 100-ns Zebra facility have shown tamping of the electrothermal instability at thicknesses of 50-60 μm (T.M. Hutchinson et al. Phys. Rev. E 2018).
A 355 nm, 1.5 ns, up to 1 kHz microchip laser system has been tested to both yield ablation spots and postionize material within a plasma plume. A 30 µJ pulse energy microchip laser successfully ablated all samples: 6601 aluminum, 316 and 304 stainless steel, and Mo metal. While visible ablation craters were observed on all samples mentioned above, the stainless-steel samples displayed visible color changes in the resolidified iron, indicating ionization with the 355 nm pulses during ablation. Additionally, when used to intercept a plasma plume of Cs 2 CO 3 made with a separate laser system, the microchip laser pulses yielded Cs + emission signal otherwise not observed. With these experiments completed, the microchip laser has been successfully verified for readiness to be integrated into the front end of a mass spectrometer system as the ion source.
Approximately 54 million gallons of radioactive and hazardous waste are stored in underground storage tanks at the U.S. Department of Energy’s (DOE’s) Hanford Site in southeastern Washington State. The Hanford Waste Treatment and Immobilization Plant (WTP) is being constructed to immobilize the waste in glass waste forms. The baseline configuration of the WTP includes a Pretreatment Facility to separate the wastes into a small volume of high-level waste (HLW) containing most of the radioactivity and a larger volume of low-activity waste (LAW) containing most of the non-radioactive chemicals. The HLW will be converted to glass in the HLW vitrification facility for ultimate disposal at a federal repository.
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