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Filtering by: Subject Reactor fuel reprocessing Degree Field Radiation Health Physics

Influence of temperature on the extraction of Pu(IV) by tri-n-butyl phosphate from acidic nitrate solutions

Creator:

Brown, M. Alex

Abstract:

The goal of Advanced Fuel Cycle Initiative program is to efficiently separate and recover actinides in attempts to reprocess irradiated nuclear fuel and reduce the necessary storage volume. In order to facilitate large-scale industrial applications of liquid-liquid separation processes, knowledge of the thermodynamic constants associated with the distribution of metal...

Resource Type:

Masters Thesis

Full Text:

Project Summary ………………………… 2.1 Irradiated Fuel and Reprocessing Chemistry …………. 2.2