Highly efficient and selective 99TcO 4 – uptake from reprocessing low-level liquid waste using a zirconium-based metal−organic framework

化学 放射性废物 裂变产物 金属有机骨架 离子交换 水溶液中的金属离子 乏核燃料 选择性 吸附 锕系元素 金属 无机化学 核化学 放射化学 离子 催化作用 有机化学
作者
Kankan Patra,Vinit K. Mittal,T.P. Valsala,Arijit Sengupta,Ashok Kumar Sahu,Darshan B. Sathe,Raj B. Bhatt
出处
期刊:Separation Science and Technology [Informa]
卷期号:58 (15-16): 2837-2845
标识
DOI:10.1080/01496395.2023.2260949
摘要

ABSTRACTEfficient and selective sequestration of pertechnetate ions (99TcO4–) from nuclear low-level waste (LLW) solution is very much desirable for the safe treatment of radioactive liquid waste. However, the separation of specific radionuclides from competitors is a huge challenge in separation science. In the nuclear fuel cycle, 99TcO4– is one of troublesome fission products due to long half-life, large inventory in spent fuel, significant radiation hazards, and high environmental mobility of 99TcO4– ions. Recently, the metal−organic framework (MOFs) has shown significant potentials toward 99TcO4– removal. So far, most of the studies were reported using ReO4– ions, an inactive surrogate of 99TcO4– ions, and very few MOF materials are applied for real-time 99TcO4– sequestration from nuclear waste solution in the presence of extreme conditions. Herein, we report 99TcO4– ion removal from low-level liquid nuclear waste solution using zirconium-based metal−organic framework UIO-66-NH2. The material has exhibited fast kinetics and record selectivity toward 99TcO4– ions, making the adsorbent highly promising.HIGHLIGHTS Successful synthesis of zirconium-based metal−organic framework UIO-66-NH2/UIO-66-NH3+ was carried out using the solvothermal method.Characterization of zirconium-based metal−organic framework UIO-66-NH2/UIO-66-NH3+ was carried out using PXRD, SEM, EDX, and elemental analysis.An ion exchange study of 99TcO4– ions was carried out with low-level waste (LLW) solution.UIO-66-NH2/UIO-66-NH3+ has exhibited fast kinetics and record selectivity toward 99TcO4– ions with low-level waste (LLW) solution.Feasibility and selectivity study of the TcO4− extraction process with nuclear reprocessing low-level waste (LLW) solution.KEYWORDS: UiO-66-NH2/NH3+ MOFseparation99TcO4– ionsnuclear waste solution AcknowledgmentsThe authors acknowledge U. Dani, G.M, R &WM, BARC (T), Dr. H.Pal, Professor, Homi Bhabha National Institute & Former Associate Director, Chemistry Group, BARC, Mumbai, and Dr. Biswajit Sadhu, Scientific Officer, HPD, BARC, Mumbai.Disclosure statementNo potential conflict of interest was reported by the author(s).Author informationAll the authors have given permission to the final version of the manuscript.
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