Jaime George
Pacific Northwest National Laboratory
PO Box 999
Richland, WA 99352
(509) 371-6380
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PNNL Publications
2023
- Crum J.V., J.D. Vienna, B.J. Riley, J.A. Silverstein, R.M. Kissinger, J.J. Neeway, and J.L. George, et al. 2023. "Formulation and Testing of a High-Tin Borosilicate Nuclear Waste Glass for In-Can Melting." Journal of Nuclear Materials 585. PNNL-SA-182284. doi:10.1016/j.jnucmat.2023.154643
- Riley B.J., N.L. Canfield, M. Peterson, J.L. George, S. Chong, and J.V. Crum. 2023. Crystalline versus Glassy Nature of Iron Phosphate Waste Forms Subjected to Different Slow Cooling Curves. PNNL-34917. Richland, WA: Pacific Northwest National Laboratory. Crystalline versus Glassy Nature of Iron Phosphate Waste Forms Subjected to Different Slow Cooling Curves
- Skerratt-Love K.L., J.L. George, A. Bell, F. Sweeney, D.A. Cutforth, C.E. Lonergan, and D.R. Dixon, et al. 2023. "The effects of phosphorus pentoxide additions on the thermal, rheological and structural properties of sodium borosilicate glass." Journal of Non-crystalline Solids 600. PNNL-SA-170708. doi:10.1016/j.jnoncrysol.2022.121999
2022
- Cholsaipant P., J.L. George, D. Kim, and A.A. Kruger. 2022. "Volatility of sodium, potassium, and cesium perrhenates determined by thermogravimetry." Journal of Thermal Analysis and Calorimetry 147. PNNL-SA-151081. doi:10.1007/s10973-021-11173-8
2020
- George J.L., D. Kim, and A.A. Kruger. 2020. "Effects of iron oxalate on rhenium incorporation into low-activity waste glass." Journal of Non-crystalline Solids 545. PNNL-SA-147196. doi:10.1016/j.jnoncrysol.2020.120257
- Luksic S.A., R. Pokorny, J.L. George, P.R. Hrma, T. Varga, L.R. Reno, and A.C. Buchko, et al. 2020. "In situ characterization of foam morphology during melting of simulated waste glass using X-ray Computed Tomography." Ceramics International 46, no. 11:17176-17185. PNNL-SA-150049. doi:10.1016/j.ceramint.2020.02.215
2019
- Parruzot B., J.V. Ryan, J.L. George, R.K. Motkuri, J.F. Bonnett, L.M. Seymour, and M.A. Derewinski. 2019. "Multi-glass investigation of Stage III glass dissolution behavior from 22 to 90 °C triggered by the addition of zeolite phases." Journal of Nuclear Materials 523. PNNL-SA-138413. doi:10.1016/j.jnucmat.2019.05.050
2017
- Riley B.J., J.O. Kroll, J.A. Peterson, D.A. Pierce, W.L. Ebert, B.D. Williams, and M. Snyder, et al. 2017. "Assessment of lead tellurite glass for immobilizing electrochemical salt wastes from used nuclear fuel reprocessing." Journal of Nuclear Materials 495. PNNL-SA-125402. doi:10.1016/j.jnucmat.2017.08.037