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Investigation of 99Mo potential production via UO2SO4 liquid target irradiation in a 5 MW nuclear research reactor

from uranyl sulfate solutions: Minimum-column-volume design method. J. Chromatogr. A , 1309 , 1–14. DOI: 10.1016/j.chroma.2013.08.023. 28. Dale, G. E., Dalmas, D. A., Gallegos, M. J., Jackman, K. R., Kelsey, C. T., May, I., Reilly, S. D., & Stange, G. M. (2012). 99Mo separation from high-concentration irradiated uranium nitrate and uranium sulfate solutions. J. Ind. Eng. Chem. Res ., 51 , 13319–13322. DOI: 10.1021/ie3008743. 29. Wu, D., Landsberger, S., Buchholz, B. A., & Vandegrift, G. F. (1994). Processing of LEU targets for 99 Mo production

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