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普雷克斯(PUREX)水法后处理中几种重要元素行为的理论探讨 被引量:7

THE DISCUSSION OF BEHAVIOR OF SOME IMPORTANT ELEMENTS IN PUREX PROCESS
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摘要 从热力学和动力学方面探讨了乏燃料溶解液、共去污溶剂萃取、铀钚分离中某些重要元素的化学行为。乏燃料溶解时亚硝酸浓度可从开始约3×10-2mol/L降至终点时的2×10-5mol/L,计算出NO-3-HNO2电对的溶解终点电位为1.133伏,表明终点时溶液具有更强的氧化性。由此计算了溶解液中约含3%Pu(Ⅵ)和47%Np(Ⅵ)。大部分碘将以I2形式存在,只有当亚硝酸浓度极低的情况下才会生成少量IO-3。钌将以Ru(Ⅵ)形式存在,在水相硝酸中几乎不可能把Ru(Ⅳ)氧化至Ru(Ⅷ)。在共去污萃取段当HNO3为2mol/L时约有20%Np(Ⅴ)氧化至Np(Ⅵ),3mol/LHNO3时将有70%的Np(Ⅴ)氧化至Np(Ⅵ)。铀钚分离中当用U(Ⅳ)作还原剂时,计算了Pu(Ⅳ)与U(Ⅳ)反应的浓度平衡常数为1019.5,求得的Pu(Ⅲ)/Pu(Ⅳ)比至少为4.7×108,反应速度计算表明,该反应在4.9分内即达平衡,由此指出除水力学因素外,Pu(Ⅲ)的少量萃取是铀中除钚的另一制约因素。进入铀钚分离阶段的有机相中的镎为Np(Ⅵ),它在U(Ⅳ)和Pu(Ⅲ)的作用下很快还原至Np(Ⅴ),然后U(Ⅳ)将把Np(Ⅴ)慢还原至Np(Ⅳ? The behavior of some important elements in dissolution,co decontamination and uranium plutomium separation stages from the thermodymamic and Kinetic points of view is discussed.During the dissolution of spent fuel,the concentration of nitrous acid might decrease sharply from 3×10 -2 mol/L at beginning down to 2×10 -5 mol/L at the end.The potential of NO - 3 HNO 2 half reaction in the final dissolution solution is estimated to be 1.133V.Based on the above potential,the possible valence states of Np、 Pu、I 2、Ru in dissolution solution are predicted,the Pu(Ⅳ) and Np(Ⅵ) about 3% and 47% of its total amount respectively,the iodine existing mainly as I 2 and iodate possibly appearing only under extreme condition of very low nitrous acid concentration,the Ru existing only in the form of Ru(Ⅳ),generally impossible to be oxidized to Ru(Ⅷ) in the aqueous solution of nitric acid.Depending on the contact time in the co decontamination stage,about 20% Np(Ⅴ) could be oxidized to Np(Ⅵ) when nitric acid is 2mol/L,and 70% Np(Ⅵ) when nitric acid is 3 mol/L in the extraction section of co decontamination extractor.In the separation stage,the equilibrium constant of Pu(Ⅳ) reduction with U(Ⅳ) is calculated with K c about 10 19.5 ,the reduction process reaching equilibrium within 5 min.In the given condition the ratio of Pu(Ⅲ) to Pu(Ⅳ) is 4.7×10 8.It indicates that,beside hydrodymamic effect,the little extraction of Pu(Ⅲ) is another restriction factor for having high separation factor of Pu from Uand Pu(Ⅲ)in the Separation stage, and then, the Np(Ⅴ)is Velatively slow to be veduced to Np(Ⅳ) by U(Ⅵ),The Np(Ⅵ) coming from the first extractor could be quickly reduced to Np(Ⅴ) by U(Ⅳ) and Pu(Ⅲ),therefore, a mixture of Np(Ⅴ) and Np(Ⅳ) in the Pu product of separation stage would be obtained,the Np(Ⅳ) might be dominated if resident time is long enough.The factor causing much more consumption of U(Ⅳ) than the stoichiometric equation is discussed and suggested that the action of Tc for excess consumption of U(Ⅳ) needs more careful investigation.
出处 《核科学与工程》 CSCD 北大核心 1999年第2期164-174,共11页 Nuclear Science and Engineering
关键词 乏燃料 后处理 锕系元素 裂变产物 水法 reprocessing attinides fission products
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参考文献4

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