scholarly journals Solvent extraction of thorium from nitrate solutions by dibutyl butylphosphonate in Isopar H

1982 ◽  
Author(s):  
J.E. Freer ◽  
D.H. Crump ◽  
K.M. Axler ◽  
D.G. Clifton ◽  
Hayter S.W. ◽  
...  
1966 ◽  
Vol 44 (4) ◽  
pp. 521-525 ◽  
Author(s):  
A. Aboul-Seoud ◽  
M. Doheim

The distribution coefficients of aniline between n-heptane and aqueous sodium nitrate solutions were measured at different temperatures. The activity coefficients of aniline in aqueous sodium nitrate solutions were determined. The effect of sodium nitrate on the dissociation of the anilinium ion was studied at different temperatures by a modified distribution method. Attention was directed to the choice of the extracting solvent and of the analytical method. The effect of the presence of undissociated anilinium ions on the distribution coefficients was taken into consideration.K0, Kb, ΔH, ΔF, and ΔS for the dissociation of the anilinium ion were evaluated.


2017 ◽  
Vol 58 (2) ◽  
pp. 287-290 ◽  
Author(s):  
Pan-Pan Sun ◽  
Byoung-Jun Min ◽  
Sung-Tae Kim ◽  
Sung-Yong Cho

1991 ◽  
Vol 45 ◽  
pp. 383-391 ◽  
Author(s):  
Ting-Chia Huang ◽  
Teh-Hua Tsai ◽  
Manfred Mühlstädt ◽  
Kari Rissanen ◽  
Katri Laihia ◽  
...  

1973 ◽  
Vol 35 (4) ◽  
pp. 1317-1326 ◽  
Author(s):  
M.K. Chmutova ◽  
B.F. Myasoedov ◽  
B.Ya. Spivakov ◽  
N.E. Kochetkova ◽  
Yu.A. Zolotov

2007 ◽  
Vol 561-565 ◽  
pp. 1733-1736 ◽  
Author(s):  
S.M. McDeavitt ◽  
A. Parkison ◽  
A.R. Totemeier ◽  
J.J. Wegener

The Uranium Extraction (UREX) family of processes uses solvent extraction techniques designed to partition spent uranium and transuranic (TRU) isotopes from fission product waste. Once separated, the collective TRU elements (Np, Pu, Am, and Cm) can be recycled in advanced nuclear energy systems. A zirconium matrix cermet is proposed as a fuel form for this application. Processing methods have been designed to convert the TRU product and spent Zircaloy cladding into feed materials for the hot extrusion of the cermet fuel pins. The TRU conversion process is being developed using a surrogate mixture of uranium and cerium nitrate solutions to generate mixed oxide microspheres. The Zircaloy recovery process is a hydride-dehydride method that is being demonstrated at the bench scale. The powder products from these methods may be combined through hot extrusion into a cermet composite; demonstration experiments using zirconium powder and zirconia microspheres have been completed.


2001 ◽  
Vol 89 (7) ◽  
Author(s):  
R.A. Kuznetsov ◽  
H.S. Han ◽  
U.J. Park ◽  
S.J. Park ◽  
A.N. Pakhomov

The extraction of strontium and yttrium by a 0.2 M solution of dicyclohexano-18-crown-6 (DCH18C6) in


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