γ辐照对TiAP-nDD体系中Zr保留行为的影响及机理研究OA
Effect and Mechanism of γ-irradiation on Zr Retention Behavior in Tri-isoamyl Phosphate-(n-dodecane)System
为探讨TiAP及其辐解产物与 Zr(Ⅳ)的相互作用方式,探明相关反应机理,本文以60Co为 γ辐照源,研究不同条件下辐照对 TiAP-nDD萃取和反萃 Zr(Ⅳ)行为的影响规律,并通过理论计算探讨了 TiAP及其辐解产物与 Zr(Ⅳ)的相互作用方式.结果表明:在本实验考察的吸收剂量范围内(0~500 kGy),吸收剂量≥200 kGy的 γ辐照会导致 TiAP对 Zr(Ⅳ)达到萃取平衡的时间一定程度增加;Zr的萃取分配比及其在有机相的保留值均随吸收剂量增加而增加;硝酸的存在有利于 TiAP对 Zr(Ⅳ)的萃取;当吸收剂量≥50 kGy时,Zr(Ⅳ)的萃取分配比随温度、金属离子初始浓度的增加而增加;吸收剂量为 50 kGy时,剂量率的变化对TiAP萃取 Zr(Ⅳ)无显著影响.此外,分子动力学模拟和密度泛函理论计算证明,TiAP的辐解产物——DiAP-是导致 Zr保留的主要原因.上述研究结果可加深对 TiAP辐解及辐照对萃取体系中 Zr保留行为的认识,并为TiAP在乏燃料后处理中的应用前景提供有价值的数据支撑.
The solvent extraction-based wet process is extensively utilized in spent fuel reprocessing,rendering the selection of extractants with outstanding extraction performance and robust chemical/radiation stability imperative.Tri-iso-pentyl phosphate(TiAP),a higher homologue of tri-butyl phosphate(TBP),boasts lower water solubility than TBP.It not only exhibits superior selectivity and extraction efficiency toward U(Ⅵ)and Th(Ⅳ)but also is less susceptible to third-phase formation during the extraction process.Consequently,TiAP is regarded as a highly promising alternative to TBP in the wet reprocessing of thorium-based nuclear fuel.In the spent fuel reprocessing process,extractants and their extraction systems are subjected to intense irradiation by various rays.This harsh irradiation environment inevitably induces changes in the molecular structure of extractants,such as chemical bond cleavage or recombination,thereby generating a series of radiolysis products.These radiolysis products tend to complex with metals,leading to difficulties in stripping and metal retention.As a major fission product in nuclear reactions,zirconium(Zr)can also be partially extracted by TBP,which impairs the decontamination efficiency of the extractant.Existing studies on irradiated TiAP primarily focus on evaluating its physicochemical properties or actinide extraction performance,leaving a research gap regarding metal ion retention—an aspect crucial for assessing extractant reusability.To address this gap,this study employed 60Co as the γ-irradiation source.Combined with solvent extraction,inductively coupled plasma optical emission spectrometry(ICP-OES)was used to determine the concentration of metal ions in the aqueous phase and calculate the extraction distribution ratio.The effects of extraction time,temperature,absorbed dose,dose rate,and aqueous acidity on Zr(Ⅳ)extraction and retention by irradiated TiAP were systematically investigated.Additionally,molecular dynamics(MD)simulation and density functional theory(DFT)calculation were integrated to explore the interaction modes between TiAP(along with its radiolysis products)and Zr(Ⅳ),as well as the underlying reaction mechanisms.The results demonstrat that within the absorbed dose range of 0-500 kGy,γ-irradiation with an absorbed dose of≥200 kGy prolonged the time required for TiAP to reach Zr(Ⅳ)extraction equilibrium.Both the Zr extraction distribution ratio and its retention in the organic phase increase with the elevation of absorbed dose.The presence of nitric acid facilitates TiAP-mediated Zr(Ⅳ)extraction.For TiAP irradiated with an absorbed dose of≥50 kGy,the Zr(Ⅳ)extraction distribution ratio increases with rising temperature and initial metal ion concentration.At an absorbed dose of 50 kGy,the dose rate exerts no significant impact on Zr(Ⅳ)extraction by TiAP.Furthermore,MD simulation and DFT calculation reveal that DiAP-,a radiolysis product of TiAP,is the primary contributor to Zr retention.These findings further enrich the understanding of TiAP's radiolysis behavior and provide valuable data support for its potential application in spent fuel reprocessing.
肖楚妍;石仕泷;宋嘉健;张润宇;李飞泽;杨远友;刘宁;廖家莉
四川大学 原子核科学技术研究所 辐射物理及技术教育部重点实验室,四川 成都 610064四川大学 原子核科学技术研究所 辐射物理及技术教育部重点实验室,四川 成都 610064四川大学 原子核科学技术研究所 辐射物理及技术教育部重点实验室,四川 成都 610064四川大学 原子核科学技术研究所 辐射物理及技术教育部重点实验室,四川 成都 610064四川大学 原子核科学技术研究所 辐射物理及技术教育部重点实验室,四川 成都 610064四川大学 原子核科学技术研究所 辐射物理及技术教育部重点实验室,四川 成都 610064四川大学 原子核科学技术研究所 辐射物理及技术教育部重点实验室,四川 成都 610064四川大学 原子核科学技术研究所 辐射物理及技术教育部重点实验室,四川 成都 610064
能源科技
磷酸三异戊酯γ辐照Zr保留萃取
tri-iso-pentyl phosphateγ-irradiationZr retentionextraction
《原子能科学技术》 2026 (5)
1014-1026,13
评论