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2001•Indian Journal of Chemical TechnologyOpen access

Modelling of Np(VI) and Np(IV) distribution coefficients in 30% TBP/n-dodecane/nitric acid/water biphasic purex system

Shekhar Kumar, S. B. Koganti

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Abstract

In contemporary designs of flowsheets for reprocessing the spent nuclear fuels, neptunium is often termed as a contaminant. During partitioning of uranium and plutonium, its behaviour can be controlled by chemical means. Still its distribution in Purex extraction system is important. In this paper, reported data have been analysed and unique empirical equations for predicting neptunium distribution in 30% TBP/n-dodecane system are reported.

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What this paper is about

In contemporary designs of flowsheets for reprocessing the spent nuclear fuels, neptunium is often termed as a contaminant. During partitioning of uranium and plutonium, its behaviour can be controlled by chemical means. Still its distribution in Purex extraction system is important. In this paper, reported data have been analysed and unique empirical equations for predicting neptunium distribution in 30% TBP/n-dodecane system are reported.

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Available abstract

In contemporary designs of flowsheets for reprocessing the spent nuclear fuels, neptunium is often termed as a contaminant. During partitioning of uranium and plutonium, its behaviour can be controlled by chemical means. Still its distribution in Purex extraction system is important. In this paper, reported data have been analysed and unique empirical equations for predicting neptunium distribution in 30% TBP/n-dodecane system are reported.

Key concepts: PUREX, Neptunium, Chemistry, Nitric acid, Plutonium, Uranium, Dodecane, Radiochemistry

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Modelling of Np(VI) and Np(IV) distribution coefficients in 30% TBP/n-dodecane/nitric acid/water biphasic purex system — Research Paper | ScholarLens