Comparison of Extraction Behavior of Neptunium from Nitric Acid Medium Employing Tri-n-Butyl Phosphate and N,N-dihexyl Octanamide as Extractants

被引：21

作者：

Kumari, Neelam ^{[1
]}

Pathak, P. N. ^{[1
]}

Prabhu, D. R. ^{[1
]}

Manchanda, V. K. ^{[2
]}

机构：

[1] Bhabha Atom Res Ctr, Div Radiochem, Bombay 400085, Maharashtra, India

[2] Sungkyunkwan Univ, Dept Energy Sci, Suwon, South Korea

来源：

SEPARATION SCIENCE AND TECHNOLOGY | 2012年 / 47卷 / 10期

关键词：

dialkyl amide; neptunium; plutonium; reprocessing; TBP; uranium; PUREX PROCESS CONDITIONS; CATALYZED OXIDATION; TBP EXTRACTION; NITROUS-ACID; KINETICS; URANIUM; NP(IV); AMIDES; U(VI); CYCLE;

D O I：

10.1080/01496395.2011.653034

中图分类号：

O6 [化学];

学科分类号：

0703 ;

摘要：

Extraction behavior of neptunium has been compared for tri-n-butyl phosphate (TBP) and N,N-dihexyl octanamide (DHOA) extractants as a function of nitric acid concentration (0.5 - 6M HNO3), uranium loading (50 and 300 g/L relevant to Pu rich fast reactor and Pressurized Heavy Water Reactor, PHWR spent fuels, respectively), and in the presence of oxidizing and reducing agents. These studies suggest the possibility of co-recovery of U(VI), Pu(IV) and Np(IV) from spent fuel dissolver solutions (of Pu rich fuels) employing DHOA as extractant.

引用

页码：1492 / 1497

页数：6

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