Studies on the Development of a Flow-Sheet for AHWR Spent Fuel Reprocessing Using TBP

被引：9

作者：

Dhami, P. S. ^{[1
]}

Jagasia, Poonam ^{[1
]}

Panja, Surajit ^{[1
]}

Achuthan, P. V. ^{[1
]}

Tripathi, S. C. ^{[1
]}

Munshi, S. K. ^{[1
]}

Dey, P. K. ^{[1
]}

机构：

[1] Bhabha Atom Res Ctr, Fuel Reproc Div, Mumbai 400085, Maharashtra, India

来源：

SEPARATION SCIENCE AND TECHNOLOGY | 2010年 / 45卷 / 08期

关键词：

AHWR; HAN; PUREX; solvent extraction; spent fuel reprocessing; TBP; THOREX; THORIUM;

D O I：

10.1080/01496391003689462

中图分类号：

O6 [化学];

学科分类号：

0703 ;

摘要：

The present paper describes the results of solvent extraction studies carried out in batch mode to collect data on distribution of uranium, plutonium, and thorium using 5% TBP in n-dodecane. Extraction studies are carried out from feed solutions having bulk thorium containing aluminum and fluoride ions in 3.00-4.00M nitric acid at concentration levels anticipated in feed solutions during Advanced Heavy Water Reactor (AHWR) spent fuel reprocessing. Studies are carried out under varied experimental conditions. Parameters such as organic to aqueous phase ratio during extraction, concentration of nitric acid for scrubbing co-extracted thorium from loaded organic phase etc., are studied in detail. Hydroxylamine nitrate is selected for reductive stripping of plutonium in preliminary studies. Reagent mixture containing 0.30M HAN+0.60M HNO3 and 0.20M N2H4 is found to be optimum for plutonium partitioning. This paper also describes the extraction and stripping of uranium and plutonium in co-current mode. The extraction behavior of relevant fission products is studied from a simulated feed solution. A preliminary study on a few commercially available reducing agents is also included. These data are useful in developing a flow-scheme for the recovery of uranium and plutonium from spent fuel originating from AHWR.

引用

页码：1147 / 1157

页数：11

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