FIELD: recovery of highly active liquid waste formed in hydrometallurgy method for reconditioning irradiated nuclear fuel.
SUBSTANCE: proposed method involves mixing of source cesium-137 re-extract with concentrated orthophosphoric acid in molar proportion in terms of cesium oxide and phosphor pentoxide maximum 0.5, repeated conduction of "porous alumosilicate glass-crystal block saturation - drying in its pores" cycle followed by calcination of cesium salt. This method enables solidifying cesium-137 re-extract to obtain porous material without cesium salting out on its surface at drying stage reducing cesium vapor volatility by minimum 80 times without impairing basic characteristic of cesium-137 re-extract solidification product (leaching rate).
EFFECT: reduced volatility of cesium vapors at calcination stage without impairing its leaching rate.
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