普里涅普罗夫斯克化工厂处理铀矿的放射性废料中铀的吸附

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引用次数: 2

摘要

摘要对生产协会“普里涅普罗夫斯基化工厂”(PA PCP)积累的放射性废物中铀吸附的可能性进行了研究。说明了利用含有苄基吡啶官能团的AMP阴离子矿(由斯莫里国营企业制造)从Zapadnoye(西部)尾矿库倾倒的放射性废物酸性浸出所产生的纸浆中吸附浸出铀的概念可能性。在15%硫酸和1.5%硝酸混合酸浸废工艺中,铀的回收率为70% ~ 80%。采用吸附浸出可使回收率提高15%。采用含有2-羟乙基二甲基铵官能团的苯乙烯-二乙烯基苯共聚物为基材的AM-p-2强碱大孔阴离子矿,对中亚尔尾矿地上、地下水中铀的回收进行了评价。该尾矿库矿浆经选矿后几乎未中和,具有放射性水的酸性反应。尾矿库中铀的活性浸出及其向地下水迁移的能力对环境造成危害。结果表明,当铀浓度在间隙水中为7 mg/l,地下水为4 mg/l时,其分布因子可达~2 000。给出了用改性植物基磷酸盐阳离子矿回收103号楼地下室放射性污染水中铀的评价结果。该建筑受到严重污染,需要优先处理和进一步拆除。静态模式下铀的吸附量为~20 mg/g,分配系数为~4 800。所得结果可作为103号楼地下抽水前对污水进行除污处理的方法和技术依据。研究表明,在解决原普里捷涅普罗夫斯基化工厂尾矿场地修复和放射性废物处理问题时,应用吸附材料是最方便和最有前途的选择性回收铀的方法。
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Uranium sorption from radioactive waste of uranium ore processing at Pridneprovsk Chemical Plant
Abstract. The research results were generalized regarding the possibility of uranium sorption from radioactive waste accumulated at Production Association “Pridneprovsky Chemical Plant” (PA PCP). The conceptual possibility was illustrated for sorption leaching of uranium from pulps produced by acidic leaching of radioactive waste dumped at Zapadnoye (Western) tailing impoundment using AMP anionite contained benzyl pyridinium functional groups (manufactured by Smoly State Enterprise). Uranium recovery was 70 % to 80 % during waste acidic leaching with the mixture of 15 % sulphuric and 1.5 % nitric acids. Application of sorption leaching allowed the recovery increase up to 15 %. Uranium recovery was assessed from upper ground and underground water of Centralny Yar tailing site using AM-p-2 strong base macroporous anionite (produced by Smoly SP) based on styrene-divinyl benzene copolymer with 2-hydroxyethyl-dimethylammonium functional groups. This tailing impoundment features acidic reaction of radioactive water since the pulp was almost not neutralized after ore processing. It poses an environmental hazard due to active uranium leaching from the tailing impoundment body and its ability to migrate into groundwater. It was found that the distribution factor may attain ~2 000 for uranium concentration 7 mg/l in interstitial water and 4 mg/l in underground water. Assessment results were given regarding uranium recovery from radioactively contaminated water accumulated in the basement of building No. 103 using phosphate cationite based on modified plant material. The building is extremely contaminated and of top-priority for treatment and further dismantling. Sorbent capacity by uranium achieved in static mode was ~20 mg/g with distribution factor ~4 800. The results obtained may be proposed as the reasoning for the method and technology intended to decontaminate polluted water before it would be pumped from underground rooms of building No. 103. The research performed has shown that application of sorption materials is the most expedient and promising method for selective uranium recovery when solving the problems of tailing site remediation and handling radioactive waste of the former Pridneprovsky Chemical Plant.
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