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1 Introduction Tributyl phosphate (TBP) is commonly used solvent in nuclear fuel reprocessing of nuclear industry. The extraction and purification of uranium, plutonium, thorium and other rare earth elements in PUREX process involves the extraction of solute molecule from aqueous nitric acid solution using 30 % TBP in paraffinic diluent. During this process traces amount of TBP is dissolved in the aqueous nitric acid phase due to solubility of TBP. The presence of TBP even in traces in the aqueous phase is undesirable, as it can lead to violent reactions. This

Radiochim. Acta 95, 559–567 (2007) / DOI 10.1524/ract.2007.95.10.559 © by Oldenbourg Wissenschaftsverlag, München Kinetics and mechanism of the plutonium catalysed nitric acid oxidation of U(IV) ions in 30% tributyl phosphate solution By V. S. Koltunov1, G. I. Zhuravleva1, V. I. Marchenko1, K. N. Dvoeglazov1, O. A. Savilova1, G. V. Koltunov1, R. J. Taylor2,∗ and M. Bankhead3 1 A. A. Bochvar All-Russia Institute of Inorganic Materials, VNIINM, PO Box 369, Moscow 123060, Russia 2 Nexia Solutions Ltd., British Technology Centre, Seascale, CA20 1PG, UK 3 Nexia

Radiochimica Acta 27, 2 2 3 - 2 2 7 (1980) © Akademische Verlagsgesellschaft, Wiesbaden 1980 An Infrared Study of Zirconium Retention in 30% Tributyl Phosphate By J. H. MEISENHELDER and A. A. SlCZEK, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (Received February 7 ,1980; revised March 24 ,1980) Zirconium /Infrared spectra/TBP/Fuel reprocessing /Degradation Summary The retention of zirconium in 30% TBP/nDD as a function of the age of zirconium organic solutions was studied by observing spectra in the infrared region of

Radiochimica Acta 27, 2 1 7 - 2 2 1 (1980) © Akademische Verlagsgesellschaft, Wiesbaden 1980 Zirconium Retention in 3 0 % Tributyl Phosphate/n-Dodecane By A. A. SlCZEK and J. H. MEISENHELDER, Argonne National Laboratory, 9700 South Cass Avenue, Argonne, Illinois 60439 (Received February 7, 1980; revised March 24,1980) Zirconium/TBP/Solvent extraction /Fuel reprocessing /Degrada- tion Summary Retention of zirconium in 30% TBP/nDD as a function of the age of zirconium organic solutions was studied by comparing distribu- tion coefficients obtained from

Radiochimica Acta35, 53 -56 (1984) © R. Oldenbourg Verlag, München 1984 Polarographic Behaviour of Uranium (VI) in Tributyl Phosphate Organic Solutions By C. A. DEGUELDRE and M. MEKLATI, Division Mate'riaux Nucleates, C.E.N., Blvd. Frantz Fanon, Alger, Algerie (Received May 18, 1983; revised October 10, 1983) Uranium /Polarography /Extraction/Tributyl phosphate /Propylene carbonate /N, N-Dimethylacetamide Summary U(VI) determination by D.C. and differential pulse polarography was studied in the organic solutions derived from tributyl phos- phate

Abstract

The present work investigates the role of increase in the basicity of organophosphorus extractant (dialkylalkyl phosphonates) on the uptake of actinides and fission products vis-à-vis tributyl phosphate (TBP), currently employed as a universal extractant. Two dialkylalkyl phosphonates viz. dibutylpropyl phosphonate (DBPrP) and dibutylpentyl phosphonate (DBPeP) were synthesized, characterized and evaluated for their solvent extraction behavior towards U(VI), Th(IV), Eu(III) and Tc(VII) in nitric acid medium ranging from 0.01–6 M. It was observed that increasing the basicity of the phosphoryl oxygen enhanced the uptake of the actinides and the distribution coefficient values were significantly larger as compared to TBP. The limiting organic concentration (LOC) value was estimated for Th(IV) for these extractants and compared with the TBP system. The separation factors of actinides with phosphonates over Tc(VII) are distinctly better than that with TBP.

Radiochim. Acta 92, 883–887 (2004)  by Oldenbourg Wissenschaftsverlag, München Reduction kinetics of Np(VI) by n-butyraldehyde in tributyl phosphate diluted with n-dodecane By Yasutoshi Ban∗, Toshihide Asakura and Yasuji Morita Japan Atomic Energy Research Institute, Department of Fuel Cycle Safety Research, Process Safety Laboratory, Tokai-mura, Naka-gun, Ibaraki-ken, 319-1195, Japan (Received August 26, 2003; accepted in final form April 18, 2004) Np(VI) reduction / n-butyraldehyde / TBP / Reduction kinetics Summary. The reduction kinetics of Np(VI) by n

Radiochimica Acta 34, 203-206 (1983) © R. Oldenbourg Verlag, München 1983 The Solvent Extraction Behavior of Technetium, Part III. Extraction from Aqueous Salt Solutions by Tributyl Phosphate* By D. J . P R U E T T and D. R. M C T A G G A R T , Oak Ridge National Laboratory, Oak Ridge, Tennessee 37831 (Received June 2, 1983; revised July 25, 1983) Technetium /Rhenium / Tributyl phosphate /Solvent extraction / Activity coefficients Abstract The extraction of Tc(VII) by tributyl phosphate (TBP) as MTcO, (M = H, Li, Na, K, Rb, or NH, ) from aqueous

Radiochimica Acta 76, 45-53 (1997) © R. Oldenbourg Verlag, München 1997 Kinetics and Mechanism of the Oxidation of Neptunium(IV) by Nitric Acid in Tributyl Phosphate Solution By V. S. KoltunovS R. J. Taylor^*, O. A. SavllovaS G. I. Zhuravleva', I. S. Denniss^ and A, L. Wallwork^ ' A. A. Bochvar All-Russia Research Institute of Inorganic Materials, VNIINM, PO Box 369, Moscow 123060, Russia ^ Sellafield Research and Development Department, BNFL Sellafield, Seascale, Cumbria CA20 IPG, UK (Received June 20, 1996; accepted September 17, 1996) Kinetics / Rate

High Temperature Materials and Processes, Vol. 8, No. 1, 1988, 21-28 Extraction of Uranium by Emulsion Liquid Membranes Containing ß-Diketones and Tributyl Phosphate Kenichi Akiba and Junko Ohki Research Institute of Mineral Dressing and Metallurgy (SENKEN), Tohoku University, Sendai 980, Japan CONTENTS Page ABSTRACT 2 2 1. INTRODUCTION 22 2. EXPERIMENTAL 22 3. RESULTS AND DISCUSSION 2 3 3.1. Stability of Emulsion 23 3.2. Liquid-Liquid Extraction of Uranium 24 3.3 Extraction by Emulsion Liquid Membrane 24 3.4 Emulsion Liquid Membrane with Mixed