Physicochemical properties and radiolytic degradation studies on tri-iso-amyl phosphate (TiAP)

Author:

Sreenivasulu B.1,Suresh A.2,Rajeswari S.2,Ramanathan N.2,Antony M. P.2,Sivaraman Nagarajan3,Joseph M.2

Affiliation:

1. Chemistry Group, Homi Bhabha National Institute, Indira Gandhi Centre for Atomic Research, Kalpakkam-603 102, Tamil Nadu, India

2. Chemistry Group, Indira Gandhi Centre for Atomic Research, Kalpakkam-603 102, Tamil Nadu, India

3. Chemistry Group, Homi Bhabha National Institute, Indira Gandhi Centre for Atomic Research, Kalpakkam-603 102, Tamil Nadu, India , Fax: 27480065

Abstract

Abstract The solvent composed of tri-iso-amyl phosphate (TiAP) in n-dodecane (n-DD) is regarded as a promising candidate for reprocessing of spent fuel. In this context, the radiolytic degradation of a solution of TiAP in n-dodecane was investigated by irradiating the solvent to various absorbed dose levels of γ-radiation. The neat extractant or a solution of extractant in n-dodecane was irradiated in the presence of nitric acid. Physicochemical properties such as density, viscosity and interfacial tension (IFT) were measured for unirradiated and irradiated solutions. The extent of degradation was determined by measuring the variation in extraction behavior of U(VI) and Pu(IV) with irradiated solvent systems. Uranium and plutonium retention with irradiated solvents was also measured. The distribution ratio of uranium and plutonium increased with increase in absorbed dose. Effect of alpha degradation was studied by plutonium retention as a function of time using 1.1 M TiAP/n-DD. Laser desorption/ionization mass spectrometric technique was employed to identify the possible radiolytic degradation products. Similar studies were also carried out with tri-n-butyl phosphate (TBP) based solvent system under identical experimental conditions and the results are compared.

Publisher

Walter de Gruyter GmbH

Subject

Physical and Theoretical Chemistry

Reference45 articles.

1. Sood, D. D., Patil, S. K.: Chemistry of nuclear fuel reprocessing: Current Status. J. Radioanal. Nucl. Chem. Art. 203, 547 (1996).

2. Natarajan, R., Raj, B.: Fast reactor fuel reprocessing technology in India. J. Nucl. Sci. Technol. 44, 393 (2007).

3. Balasubramaniam, G., Chitnis, R., Ramanujam, A., Venkatesan, M.: Laboratory studies on the recovery of uranium-233 from irradiated thorium by solvent extraction using 5% TBP Shell Sol-T as Solvent. In Bhabha Atomic Research Centre: 1977.

4. Schmieder, H., Petrich, G.: IMPUREX: a concept for an improved PUREX proces. Radiochim. Acta. 48, 181 (1989).

5. Schulz, W. W., Burger, L. L., Navratil, J. D., Bender, K. P.: Science and technology of tributyl phosphate, Vol. 3, CRC Press, Florida (1990).

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