FIELD: nuclear power engineering; treatment of ion-exchange resins. SUBSTANCE: decontaminating solution incorporating sodium salt and acid is passed upon heating to 30 - 100 C through spent cation-exchange resin. Strippant obtained is then passed through ferrocyanide sorbent filter for decontamination, and solution is alkalized to pH = 9.5 to 11.0 to enable additional precipitation of bivalent and trivalent radionuclides from strippant. EFFECT: enhanced efficiency of radionuclide desorption from cation-exchange resin; improved cleaning of strippant from activated corrosion products. 2 cl, 1 dwg
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Authors
Dates
2004-02-20—Published
2001-11-27—Filed