摘要
乏燃料后处理碱性流程是用碳酸盐、氢氧化物等碱性物质的溶液作为介质进行乏燃料的溶解及铀、钚等元素的分离与纯化的方法。碱性条件下,乏燃料中的大部分裂变产物和次锕系元素并不溶解或者在溶解过程中转变为碳酸盐、氢氧化物沉淀。与已经实现工业化的PUREX(plutonium uranium redox extraction)酸性流程相比,碱性流程具有腐蚀性更小、流程更简单等潜在的优点。鉴于碱性流程的优点及其在乏燃料后处理中的潜在应用,日本、美国、俄罗斯、韩国等国家的科研人员已经围绕该流程开展了一些研究工作。本文首先介绍了各国建议的碱性流程的技术路线;然后逐一介绍了与主要工艺环节相关的基础研究的进展,包括乏燃料的氧化溶解、核素分离、试剂的回收等;最后对该领域面临的挑战和前景进行了讨论。
The alkaline process of spent nuclear fuel(SNF)reprocessing refers to reprocessing methods that use the alkaline solution of carbonates or hydroxides as the media to conduct the dissolution of SNF and subsequent separations of uranium,plutonium and other elements.Most of the fission products and minor actinides are either insoluble or changed to insoluble carbonates or hydroxides during the alkaline dissolution of SNF,indicating that the resulted dissolver solution contains less amount of fission and minor actinide elements.Thus,the solution is less radioactive and less corrosive in contrast to the acidic dissolver solution of commercial PUREX(plutonium uranium redox extraction)process.Due to advantages of the alkaline process and its important potential application in SNF reprocessing,researchers from Japan,Russia,the United States,South Korea,etc.have carried out some research work around this reprocessing method.This paper will review technical routes of the alkaline process proposed by these researchers and research progress related to the main processes such as oxidation dissolution of SNF,separation technologies and recovery of used reagents.The challenges and prospects in this field are also discussed.
作者
韩哲
高原
王春晖
邱杰
何辉
矫彩山
HAN Zhe;GAO Yuan;WANG Chun-hui;QIU Jie;HE Hui;JIAO Cai-shan(School of Nuclear Science and Technology,Xi’an Jiaotong University,Xi’an 710049,China;China Institute of Atomic Energy,P.O.Box 275(26),Beijing 102413,China;College of Nuclear Science and Technology,Harbin Engineering University,Harbin 150001,China)
出处
《核化学与放射化学》
CAS
CSCD
北大核心
2024年第1期1-19,I0004,共20页
Journal of Nuclear and Radiochemistry
基金
国家自然科学基金资助项目(No.U1967219,22076152,21806127)
陕西省自然科学基金资助项目(No.2020JM-016)。
关键词
乏燃料后处理
碱性流程
乏燃料的溶解
锕系元素的分离
reprocessing of spent nuclear fuel
alkaline process
oxidative dissolution
actinide separation
