Critical Mineral Extraction from Waste Streams: Li, REE, Ni, and V
Critical Mineral Workshop, Virtual, November 8-11, 2021.
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Critical Mineral Workshop, Virtual, November 8-11, 2021.
American Chemical Society (ACS) presentation.
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TMS 2022, Virtual, February 27–March 3, 2022
ACS Spring 2022 National Meeting, Virtual, March 20-24, 2022
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2022 Carbon Management Project Review Meeting, Pittsburgh, PA, August 15-19, 2022
Enrico Fermi Nuclear Generating Station is a nuclear power plant on the shore of Lake Erie. On October 5, 1966, Fermi 1, a prototype fast breeder reactor, suffered a partial fuel meltdown (no radioactive material was released). As a result, 34 metric tons of sodium-bonded blanket material from the decommissioned Fermi-1 reactor were shipped to and are currently stored at the Idaho Nation Lab (INL). This material is currently awaiting removal from the state of Idaho by 2035. In its current state, the Fermi-1 material is not suitable for disposal due to the reactive characteristic of its bond sodium. This work demonstrates removal of bond sodium from an entire full-length unirradiated Fermi-1 outer radial blanket assembly using a gravity assisted melt-drain-evaporate (MEDE) treatment process. Quantitative and qualitative analyses were performed to characterize the extent of sodium removal from the blanket material following MEDE treatment.
Disclosed herein is a method and apparatus that uses a brine from a well that is used to both generate electricity and recover valuable minerals present in the brine. The method and apparatus uses a hydrophobic membrane to separate water vapor from the brine to concentrate the brine that is then used to recover the minerals.
A one-dimensional finite-element model based on the MOOSE framework has been constructed, and overall transport estimates are predicted based on available diffusivities and sorption isotherms in the extant literature. The predicted transport profiles are compared to experimental results, where such results are available, including total inventory analysis of gamma emitters, liquid scintillation results for Sr-90 concentrations, radial deconsolidation leach-burn-leach within compacts, tomographic reconstructions based on detailed gamma scanning and destructive physical sampling of several rings. The magnitude of expected transport to the sink ring is generally predicted by the model for silver and cesium, however, modeled detailed concentration profiles are not consistent with experimental results. Strontium and europium transport is not well characterized by model results.
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