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作 者:肖松涛[1] 叶国安[1] 罗方祥[1] 刘协春[1] 杨贺[1] 兰天[1] 孟照凯[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73-79,共7页Journal of Nuclear and Radiochemistry
摘 要:为了进一步优化Purex流程,研究了甲醛肟(FO)的硝酸水溶液对30%TBP/煤油中Pu(Ⅳ)的还原反萃取行为,考察了FO浓度、两相接触时间、两相相比、反萃液硝酸浓度、NO3-浓度、有机相U浓度和温度对Pu(Ⅳ)的还原反萃的影响。结果表明:延长两相接触时间能显著提高Pu(Ⅳ)的反萃率,增加甲醛肟的浓度、降低反萃液酸度、降低NO3-浓度、增加有机相U浓度和升高温度也对Pu(Ⅳ)的反萃率有一定的提高。采用16级逆流反萃取实验(还原反萃段12级,补充萃取段4级),模拟Purex流程1B槽U/Pu分离工艺,在相比(1BF∶1BX∶1BS)为4∶1∶1的条件下,U和Pu的回收率均大于99.99%;铀中去钚的分离因子SF(Pu/U)=1.0×104;钚中去铀的分离因子SF(U/Pu)=8.3×104。FO作为新型络合-还原反萃取剂,可有效实现铀钚分离。In order to optimize the Purex process, the reduction stripping behavior of Pu(Ⅵ) from 30% TBP/OK with formoxmine (FO) was investigated. The effect of temperature, FO concentration, HNO3 concentration, NO;- concentration, U concentration in organic phase, contacting-time and phase ratio was studied, respectively. The results show that the stripping percentage of Pu(Ⅵ) increases.with the phase contacting-time, FO concentration, U concentration in organic phase and the temperature, and decreases with HNO3 concentra- tion, NO3 concentration. The separation of Pu from U by FO in 1B contactor was carried out using 16-stage counter current extraction (in which 4 stages for supplemental extraction, 12 stages for stripping). At phase ratio (1BF: 1BX :1BS) =4 :1:1, the recovery percent- ages of both U and Pu are more than 99.99%. The separation factor of Pu over U is 1.0×10^4, and the separation factor of U over Pu is 8.3 ×10^4. The present work indicates that FO as a new organic reducing and complexing agent can effectively achieve the separation of Pu from U.
分 类 号:TL241[核科学技术—核燃料循环与材料]
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