普雷克斯
乏核燃料
化学
钚
萃取(化学)
扩散
核燃料
铀
化学反应
过程(计算)
溶剂
锆
溶剂萃取
色谱法
放射化学
热力学
有机化学
材料科学
核化学
计算机科学
冶金
物理
操作系统
作者
Scott DeMuth,Robert M. Counce
出处
期刊:Aiche Journal
[Wiley]
日期:1992-06-01
卷期号:38 (6): 801-810
被引量:3
标识
DOI:10.1002/aic.690380602
摘要
Abstract The primary objective of this study was to develop and validate experimental and mathematical procedures that can be used to determine the fundamental mechanisms of the Purex (plutonium and uranium) extraction process. The mechanisms of this solvent extraction process have been established by classical chemical engineering principles. In the past, modeling of transport phenomena for the solvent extraction of spent nuclear fuel by the Purex process has typically (1) relied solely on diffusion, (2) relied solely on chemical reaction, (3) combined diffusion and chemical reaction in a semiempirical fashion, or (4) combined diffusion and chemical reaction in a nonclassical chemical engineering manner. This study was conducted with the single Purex species, aqueous Zr 4+ , to simplify the chemistry and modeling mathematics. The validated procedures and model are applicable to most all Purex species.
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