Purex流程的改进 Ⅰ.共去污单元锆、钌净化工艺  

Improvement of the Purex Process Ⅰ.Purification Process for Removal of Zirconium and Ruthenium in the Co-Decontamination Unit

作　　者：常利[1] 欧阳应根[1] 张洁萍[1] 常尚文[1] 李瑞雪[1] 刘利生[1] 郭建华[1] 王长水[1] 高巍[1] 张倩[1] 

机构地区：[1]中国原子能科学研究院放射化学研究所,北京102413

出　　处：《核化学与放射化学》2013年第2期87-91,共5页Journal of Nuclear and Radiochemistry

摘　　要：通过单级实验,研究了不同铀饱和度、酸度、温度条件下30%TBP对锆、钌的萃取规律,在此基础上确定了提高1A净化锆、钌的工艺,并进行了台架实验验证。研究结果表明:提高铀饱和度、温度和酸度有助于降低钌在30%TBP中的分配比;在30%TBP中,高铀饱和度条件下,锆分配比受铀饱和度的影响远大于水相硝酸浓度的影响;温度对锆的分配比影响不显著。当1A槽采用4mol/L硝酸进料、4mol/L硝酸洗涤时,45℃条件下,铀、钚的回收率达99.98%,钌的去污系数约达到105。The effect of uranium saturation, acidity and temperature on the extaction of Zr and Ru by 30%TBP was investigated by batch experiments. Accordingly, the process parameters were determined to improve the decontamination of Zr and Ru in 1A unit, and tested in lab-scale mixer-settler cascade. The results indicate that the increase in uranium saturation, acidity and temperature reduce the distribution ratio of Ru in 30%TBP, the effect of uranium saturation on the distribution ratio of Zr is much greater than the effect of the aqueous nitric acid under high uranium saturation, and the temperature shows no significant influence on the the distributaion ratio of Zr. At 45℃, using 4 mol/L nitric acid in feed and scrubbing solutions in the 1A mixer-settler, the recovery rate of uranium and plutonium reachs 99.98% with Ru decontamination factor of about 10s.

关 键 词：PUREX流程 1A槽 锆 钌 净化系数 

分 类 号：TL241[核科学技术—核燃料循环与材料]