Abstract
Spent light-water reactor (LWR) fuel with burnups of 9, 28 and 54 MWd/kgU were leach tested at 25°C in deionized water in a Paige apparatus. No discernible differences in long term leach rates were observed relative to burnup. An accelerated leaching period was observed during the Paige leach test of the 54 MWd/kgU spent fuel. Additionally, the 28 MWd/kgU fuel was IAEA leach-tested in five different leach solutions. Deionized water gave the highest leach rates, and calcium chloride solution gave the lowest.
Comparisons between spent fuel and borosilicate waste glass leach rates are made. In sodium bicarbonate solution, the leach rates are nearly equal and the glass becomes increasingly more resistant in calcium chloride solution, followed in order by sodium chloride solution, WIPP “B” brine and deionized water--in which the glass is two to three orders of magnitude more leach-resistant than is spent fuel.
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References
J. E. Mendel, A Review of Leaching Test Methods and the Leachability of Various Solids Media Containing Radioactive Wastes, BNWL-1765, Pacific Northwest Laboratory, Richland, WA (1973).
B. E. Paige, Leachability of Alumina Calcine Produced in the Idaho Waste Calcining Aluminum Waste, IDO-14672, Phillips Petroleum Company, Idaho Falls, ID 83401 (1966).
J. L. McElroy, K. J. Schneider, J. N. Hartley, J. E. Mendel, G. L. Richardson, R. W. McKee, and A. G. Blasewitz, Waste Solidification Program Summary Report, Volume II, Evaluation of WSEP High Level Waste Solidification Processes. BNWL-1667, Pacific Northwest Laboratory, Richland, WA 99352 (1972).
Y. B. Katayama, Spent LWR Leach Tests PNL-2982, Pacific Northwest Laboratory, Richland, WA 99352 (1979).
Y. B. Katayama, D. J. Bradley and C. O. Harvey, IAEA Leach Test of Spent LWR Fuel - A Progress Report, PNL-3713, Pacific Northwest Laboratory, Richland, WA 99352 (1979).
Y. B. Katayama, Leaching of Irradiated LWR Fuel Pellets in Deionized and Typical Groundwater, BNWL-2057, Pacific Northwest Laboratory, Richland, WA 99352 (1976).
D. J. Bradley, C. O. Harvey and R. P. Turcotte, Leaching of Actinides and Technetium from Simulated High Level Waste Glass, PNL-3152, Pacific Northwest Laboratory, Richland, WA 99352 (1979).
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© 1980 Springer Science+Business Media New York
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Katayama, Y.B., Bradley, D.J. (1980). Long-Term Leaching of Irradiated Spent Fuel. In: Northrup, C.J.M. (eds) Scientific Basis for Nuclear Waste Management. Advances in Nuclear Science & Technology. Springer, Boston, MA. https://doi.org/10.1007/978-1-4684-3839-0_39
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DOI: https://doi.org/10.1007/978-1-4684-3839-0_39
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