Controlled Pertraction of Plutonium(III) Under Reducing Conditions From Acidic Feeds Using TODGA as the Carrier Extractant

被引:14
|
作者
Panja, Surajit [2 ]
Mohapatra, P. K. [1 ]
Tripathi, S. C. [2 ]
Manchanda, V. K. [1 ]
机构
[1] Bhabha Atom Res Ctr, Div Radiochem, Mumbai 400085, Maharashtra, India
[2] Bhabha Atom Res Ctr, Fuel Reproc Div, Mumbai 400085, Maharashtra, India
关键词
actinide partitioning; liquid membrane; plutonium(III); TODGA; waste management; SUPPORTED LIQUID-MEMBRANE; N; N'; N'-TETRAOCTYL DIGLYCOLAMIDE TODGA; NUCLEAR WASTE SOLUTIONS; NITRIC-ACID; FACILITATED TRANSPORT; SOLVENT-EXTRACTION; FISSION-PRODUCTS; MOBILE CARRIER; N-DODECANE; ACTINIDES;
D O I
10.1080/01496395.2010.503223
中图分类号
O6 [化学];
学科分类号
0703 ;
摘要
Transport of Pu3+ across PTFE flat sheet supported liquid membranes (SLM) using N,N,N',N'-tetraoctyl-3-oxapentanediamide (TODGA) in n-dodecane as the carrier extractant was investigated. The feed solution was usually 3.0M HNO3 while the receiver phase contained 0.1M HNO3. In order to model the transport data, the two-phase liquid-liquid extraction experiments are also reported. A series of reducing agents viz. hydrazinium nitrate (HN), phenyl hydrazine (PH), hydroxyl ammonium nitrate (HAN), and ascorbic acid (AA) were evaluated to maintain plutonium in the +3 state in the feed, out of which phenyl hydrazine was found to be the most effective. Effectiveness of various strippants for quantitative and rapid transport of Pu was also evaluated. Additionally, the effects of feed acidity, carrier concentration, membrane thickness, effect of Pu carrier concentration, etc. were investigated. Membrane diffusion co-efficients were calculated and found to be 1.47x10-6cm2/s for Pu(III). The stability of the SLM, investigated as a function of contact time, was found to be reasonably good even after 20 days of continuous operation.
引用
收藏
页码:94 / 104
页数:11
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