Method for cleaning solution used in nuclear fuel reprocessing

Liquid purification or separation – Processes – Ion exchange or selective sorption

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252631, 423 10, 423 6, G21F 912

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043942695

ABSTRACT:
A nuclear fuel processing solution containing (1) hydrocarbon diluent, (2) tri-n-butyl phosphate or tri-2-ethylhexyl phosphate, and (3) monobutyl phosphate, dibutyl phosphate, mono-2-ethylhexyl phosphate, di-2-ethylhexyl phosphate, or a complex formed by plutonium, uranium, or a fission product thereof with monobutyl phosphate, dibutyl phosphate, mono-2-ethylhexyl phosphate, or di-2-ethylhexyl phosphate is contacted with silica gel having alkali ions absorbed thereon to remove any one of the degradation products named in section (3) above from said solution.

REFERENCES:
patent: 3112275 (1963-11-01), Pollock et al.
Goldacker, Schmieder, Steinbrunn, Stieglitz, "A Newly Developed Solvent Wash Process in Nuclear Fuel Reprocessing Decreasing the Waste Volume," Kerntechnik 18, 426, (1976).

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