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Removing Uranium and Radium from Groundwater by Ion Exchange Resins
Published in Arup K. Sengupta, Ion Exchange Technology, 2021
Dennis A. Clifford, Zhihe Zhang
The fact that anion resins treating drinking water exhibited enormous uranium removal capacity was not surprising in light of the capacity data generated from uranium ion exchange in the mining industry. There, anion resins have been used for more than forty years to concentrate uranyl sulfate and carbonate complexes from uranium leaching liquors [29]. In the in situ carbonate leaching process, uranyl carbonate solutions containing 40–250 mg/L uranium, i.e., more than 1,000 times the uranium concentrations found in water supplies, are passed downward through fixed beds of anion resin in the carbonate or chloride form. In spite of competition from carbonates, molybdates, and sulfates, nearly all of the resin sites are in the UO2(CO3)34− form at exhaustion. For example, typical uranium loading on the conventional 1.3 meq/mL capacity anion resins used was found to be 5 lb U3O8/ft3 [29]. This corresponds to 88% of the exhausted resin sites in the UO2(CO3)34− form. Similarly high (2.3–3.6 lb U3O8/ft3 resin) uranium capacities were reported by Ross and George [30] for a full-scale countercurrent anion exchange process treating mine waters containing only 8.5 mg/L uranium.
Development of fission gas release model for MOX fuel pellets with treatment of heterogeneous microstructure
Published in Journal of Nuclear Science and Technology, 2022
Yudai Tasaki, Yutaka Udagawa, Masaki Amaya
Two types of MOX fuels were fabricated using the SBR and the Micronized Master blend (MIMAS) method with the precipitation from Ammonium Uranyl Carbonate (AUC), namely the SBR-MOX and MIMAS-MOX fuels, respectively. Table 1 shows the fuel rod specifications [12].