普雷克斯
钚
混合氧化物燃料
乏核燃料
核燃料循环
核后处理
化学
废物管理
接触器
环境科学
燃料循环
萃取(化学)
放射化学
溶剂萃取
核化学
工程类
色谱法
物理
功率(物理)
量子力学
作者
Ori D. Fox,Christopher J. Jones,J. Eddie Birkett,M. J. Carrott,G. Crooks,Chris Maher,Cécile V. Roube,Robin J. Taylor
出处
期刊:Acs Symposium Series
日期:2006-06-09
卷期号:: 89-102
被引量:29
标识
DOI:10.1021/bk-2006-0933.ch006
摘要
The reprocessing of nuclear fuel using PUREX-based solvent extraction has been undertaken in the UK on an industrial scale for over forty years. Current research includes the development of modified PUREX-style flowsheets for processing ever-increasing plutonium content fuels including MOX, fast reactor and even experimental and legacy fuels. Herein, results are presented on Np recovery in single cycle PUREX flowsheets using hydroxamic acids. Flowsheets have been demonstrated on a centrifugal contactor rig. Aspects of Np chemistry relevant to the use of hydroxamic acids in process flowsheets for U/Pu(&Np) separation are reported.
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