普雷克斯
残液
镅
化学
钚
乏核燃料
铀
锕系元素
萃取(化学)
溶剂萃取
核后处理
超铀元素
核燃料循环
过程(计算)
核燃料
溶剂
放射性废物
工艺工程
放射化学
核化学
色谱法
有机化学
冶金
材料科学
工程类
计算机科学
操作系统
作者
Andreas Geist,Jean-Marc Adnet,Stéphane Bourg,Christian Ekberg,Hitos Galán,Philippe Guilbaud,Manuel Miguirditchian,Giuseppe Modolo,Chris Rhodes,Robin J. Taylor
标识
DOI:10.1080/01496395.2020.1795680
摘要
The hydrometallurgical separation concepts for the heterogeneous recycling of irradiated nuclear fuel developed in Europe are presented and discussed. Most of these concepts were developed within European collaborative projects and involve solvent extraction processes separating trivalent minor actinides (with a focus on americium) from the raffinate solution from processes such as PUREX (Plutonium Uranium Reduction Extraction) or an evolution of PUREX. Depending on the process chemistry applied, process schemes each consisting of one, two or three solvent extraction cycles are required to obtain a pure americium product. The various solvent extraction processes are briefly introduced. The most suitable choices are selected, and the process schemes are compared to one another.
科研通智能强力驱动
Strongly Powered by AbleSci AI