Physicochemical studies of the sludge of uranium conversion production were carried out to determine the possibility of its processing and return of uranium to the nuclear fuel cycle. It has been established that the sludge was mainly represented by calcium compounds: CaSO₄·2H₂O (60.1 wt%), CaCO₃ (25.1 wt%), CaF₂ (13.7 wt%), and silicon dioxide (1.2 wt%). The content of uranium in the sludge was 0.15 wt%. It was shown that it was possible to achieve high degrees of uranium extraction from the sludge using nitric acid as a leaching agent. The use of phosphorus-containing ion-exchanger Tulsion CH93 ensured the effective concentration of uranium from highly acidic pregnant leach solutions. The full dynamic exchange capacity achieved 15.7 kg m⁻³. The degree of uranium desorption by ACBM (ammonium carbonate/bicarbonate mixture) solutions was 83%. The final product was ammonium uranyl phosphate hydrate NH₄UO₂PO₄∙3H₂O with a uranium content of 52.5 wt%.

对铀转化生产的污泥进行了物理化学研究，以确定其处理和将铀返回核燃料循环的可能性。已确定污泥主要由钙化合物代表：CaSO ₄ ·2H ₂ O (60.1 wt%)、CaCO ₃ (25.1 wt%)、CaF ₂ (13.7 wt%) 和二氧化硅 (1.2 wt%) 。污泥中铀的含量为0.15wt％。结果表明，使用硝酸作为浸出剂可以从污泥中实现高程度的铀提取。含磷离子交换剂Tulsion CH93的使用保证了高酸性浸出液中铀的有效浓度。满动态交换容量达到15.7 kg m ^-3。ACBM（碳酸铵/碳酸氢盐混合物）溶液解吸铀的程度为83%。最终产物为磷酸铀酰铵水合物NH ₄ UO ₂ PO ₄ ∙3H ₂ O，铀含量为52.5 wt%。