Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
-
A. Suresh
,
B. Sreenivasulu
Abstract
As part of the studies on the development of alternate extractants for fast reactor fuel reprocessing, a mixer-settler facility for performing counter-current solvent extraction runs with radioactive materials has been set up and commissioned in our laboratory for flow sheet development experiments. Mixer-settler runs were carried out with 1.1 M TiAP/Heavy Normal Paraffin (HNP) as the solvent using the above facility to test the equipment as well as the behaviour of the solvent for continuous solvent extraction processes. Stage profile data generated for the extraction and stripping of nitric acid with TiAP based solvent have been reported. Studies carried out on the continuous counter-current extraction and stripping of U(VI) for 1.1 M TiAP/HNP-U(VI)-HNO3 system under high solvent loading conditions are also reported in this paper. Overall and stage-wise mass balance data for the above runs are also discussed.
Acknowledgement
The authors are thankful to Dr. R. Natarajan, Director, Reprocessing Group, IGCAR, for his guidance in carrying out the mixer-settler experiments. The authors are also thankful to Shri. G. Ravisankar, Head, Chemical Facilities Division, IGCAR, and his team for setting up the mixer-settler facility for flow sheet demonstration.
©2014 Walter de Gruyter Berlin/Boston
Artikel in diesem Heft
- Frontmatter
- Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
- A new 2-oxy-N,N-dioctylacetamide grafted resin for the separation of trivalent actinides from nitric acid medium
- Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
- Comparative study on the production of 68Ga from proton induced reactions on different targets: Evaluation of experimental data and model calculations
- Development of a production scale purification of Ge-68 from irradiated gallium metal
- New neutral and lipophilic technetium complexes based on a cytectrene moiety: synthesis, characterization and biological evaluation
- Degradation of morphine and codeine by gamma radiation in methanol solution
- Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
- Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
Artikel in diesem Heft
- Frontmatter
- Measurement of cross section of the 98Mo(n, γ)99Mo reaction using monochromatic thermal neutrons
- A new 2-oxy-N,N-dioctylacetamide grafted resin for the separation of trivalent actinides from nitric acid medium
- Mixer-settler runs for the evaluation of tri-iso-amyl phosphate (TiAP) as an alternate extractant to tri-n-butyl phosphate (TBP) for reprocessing applications
- Comparative study on the production of 68Ga from proton induced reactions on different targets: Evaluation of experimental data and model calculations
- Development of a production scale purification of Ge-68 from irradiated gallium metal
- New neutral and lipophilic technetium complexes based on a cytectrene moiety: synthesis, characterization and biological evaluation
- Degradation of morphine and codeine by gamma radiation in methanol solution
- Polycarbonate-based benzo-δ-sultam films for high-dose dosimetry in radiation processing
- Modeling of physico–chemical characteristics of concrete for filling trenches in radioactive waste management
