Electrolytic reduction of spent nuclear oxide fuel as part of an integral process to separate and recover actinides from fission products

被引：107

作者：

Herrmann, S. D. ^{[1
]}

Li, S. X. ^{[1
]}

Simpson, M. F. ^{[1
]}

Phongikaroon, S. ^{[1
]}

机构：

[1] Idaho Natl Lab, Cycle Programs Div, Idaho Falls, ID 83415 USA

来源：

SEPARATION SCIENCE AND TECHNOLOGY | 2006年 / 41卷 / 10期

关键词：

electrolytic reduction; oxide reduction; pyrochemical processing; electrometallurgical treatment; spent oxide fuel treatment; molten LiCl/Li2O;

D O I：

10.1080/01496390600745602

中图分类号：

O6 [化学];

学科分类号：

0703 ;

摘要：

Bench-scale tests were performed to study an electrolytic reduction process that converts metal oxides in spent nuclear fuel to metal. Crushed spent oxide fuel was loaded into a permeable stainless steel basket and submerged in a molten salt electrolyte of LiCl-1 wt% Li2O at 650 degrees C. An electrical current was passed through the fuel basket and a submerged platinum wire, effecting the reduction of metal oxides in the fuel and the formation of oxygen gas on the platinum wire surface. Salt and fuel samples were analyzed, and the extent of fission product separation and metal oxide reduction was determined.

引用

页码：1965 / 1983

页数：19