Actinides draw down process for pyrochemical reprocessing of spent metal fuel
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Suyambu Vannia Perumal
Abstract
An experimental system has been setup inside an argon atmosphere glove box to carry out studies on the actinide draw down process, an important step of the pyroprocess flow sheet. Studies have been carried out at 723 K on the extraction of uranium from LiCl-KCl eutectic salt containing 0.5% UCl3 using lithium-0.03% cadmium alloy. In these experiments, 5 L of the molten salt and 5 L of the molten alloy are fed to a single stage extractor where 250 mL of the salt and 250 mL of the alloy come into contact. A three stage stirrer having straight as well as pitched blade turbine impellers was used to mix the molten alloy and salt phases having high interfacial tension of 450 dyne/cm. The results of the studies indicate that a U extraction efficiency of 99% could be achieved.
Acknowledgement
The authors gratefully acknowledge Prof. Sreenivas Jayanti, Indian Institute of Technology Madras, Chennai for his valuable suggestions during the design and commissioning of the facility. The authors also acknowledge N. K. Pandey, M.V. Krishnaiah, Manish Chandra, N.Sivaraman and K. Sankaran of IGCAR for support in various aspects of the experiments.
©2014 Walter de Gruyter Berlin/Boston
Articles in the same Issue
- Frontmatter
- Preface
- Separation Science in Nuclear Technology in India
- Studies on extraction of actinides by unsymmetrical diamylbutyl phosphonate
- Supercritical fluid extraction of uranium and thorium from nitric acid medium using organophosphorous compounds
- Novel polymer inclusion membranes containing T2EHDGA as carrier extractant for actinide ion uptake from acidic feeds
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- Phosphonates as alternative to tributyl phosphate for the separation of actinides from fission products
- Actinides draw down process for pyrochemical reprocessing of spent metal fuel
- Spectroscopic investigations on sorption of uranium onto suspended bentonite: effects of pH, ionic strength and complexing anions
- Speciation of citric acid on anatase (TiO2)–water interface and its effect on Eu(III) sorption
- Separation of 134Cs and 137Cs from 125I solution for medical applications
- Optimization of 210Po estimation in environmental samples using an improved deposition unit
Articles in the same Issue
- Frontmatter
- Preface
- Separation Science in Nuclear Technology in India
- Studies on extraction of actinides by unsymmetrical diamylbutyl phosphonate
- Supercritical fluid extraction of uranium and thorium from nitric acid medium using organophosphorous compounds
- Novel polymer inclusion membranes containing T2EHDGA as carrier extractant for actinide ion uptake from acidic feeds
- Studies on the feasibility of using completely incinerable reagents for the single-cycle separation of americium(III) from simulated high-level liquid waste
- Phosphonates as alternative to tributyl phosphate for the separation of actinides from fission products
- Actinides draw down process for pyrochemical reprocessing of spent metal fuel
- Spectroscopic investigations on sorption of uranium onto suspended bentonite: effects of pH, ionic strength and complexing anions
- Speciation of citric acid on anatase (TiO2)–water interface and its effect on Eu(III) sorption
- Separation of 134Cs and 137Cs from 125I solution for medical applications
- Optimization of 210Po estimation in environmental samples using an improved deposition unit
