Article
Licensed
Unlicensed
Requires Authentication
Uranium, plutonium and neptunium co-recovery with high nitric acid concentration in extraction section by simplified solvent extraction process
-
M. Nakahara
Published/Copyright:
December 4, 2009
Abstract
As a part of NEXT, the behavior of Np in a simplified solvent extraction process using TBP as an extractant for U, Pu and Np co-recovery was investigated. Two approaches to Np co-recovery with U and Pu in the irradiated fast reactor core fuel using a dissolver solution in a counter current were examined. One used a feed solution with a high HNO3 concentration, and the other used a scrubbing solution with a high HNO3 concentration. The leakages of Np to the raffinate were 1.1 and 4.7% using high HNO3 concentration feed and scrubbing solutions, respectively. Simulation results based on these experiments showed that high HNO3 concentration in the feed solution is advantageous for the Np extraction because Np oxidation progresses in the feed solution before being supplied into the centrifugal contactor, and there is less effect of HNO2 at the extraction section.
Keywords: Simplified solvent extraction process; NEXT; Neptunium; Centrifugal contactor; Co-recovery
Published Online: 2009-12-04
Published in Print: 2009-12
© by Oldenbourg Wissenschaftsverlag, München, Germany
You are currently not able to access this content.
You are currently not able to access this content.
Articles in the same Issue
- Production and separation of no-carrier-added 93,94,95Tc from 9Be activated yttrium target
- Charged particle induced reaction cross section data for production of the emerging medically important positron emitter 64Cu: A comprehensive evaluation
- Determination of 126Sn half-life from ICP-MS and gamma spectrometry measurements
- Investigation of K to L shell/subshell vacancy transitions of Zn and Fe in FexZn1-x thin film alloys
- X-ray absorption spectroscopic study of trivalent and tetravalent actinides in solution at varying pH values
- Kinetic and thermodynamic studies on the adsorption of U(VI) ions on densely crosslinked poly(methacrylic acid) from aqueous solutions
- Extraction of americium(III) from nitric acid medium by CMPO-TBP extractants in ionic liquid diluent
- Uranium, plutonium and neptunium co-recovery with high nitric acid concentration in extraction section by simplified solvent extraction process
- Separation of 109Cd from silver targets by nanohematite
- An adapted purification procedure to improve the quality of 90Y for clinical use
- Novel polymer vectors of 64Cu
- Radiosynthesis of a novel potential adenosine A3 receptor ligand, 5-ethyl 2,4-diethyl-3-((2-[18F]fluoroethyl)sulfanylcarbonyl)-6-phenylpyridine-5-carboxylate ([18F]FE@SUPPY:2)
- Determination of solubility parameters of cobalt(II) and indium(III) oxinates by tracer technique
- Evaluation of trace elements in chewing tobacco and snuff using instrumental neutron activation analysis (INAA) and atomic absorption spectroscopy (AAS)
Keywords for this article
Simplified solvent extraction process;
NEXT;
Neptunium;
Centrifugal contactor;
Co-recovery
Articles in the same Issue
- Production and separation of no-carrier-added 93,94,95Tc from 9Be activated yttrium target
- Charged particle induced reaction cross section data for production of the emerging medically important positron emitter 64Cu: A comprehensive evaluation
- Determination of 126Sn half-life from ICP-MS and gamma spectrometry measurements
- Investigation of K to L shell/subshell vacancy transitions of Zn and Fe in FexZn1-x thin film alloys
- X-ray absorption spectroscopic study of trivalent and tetravalent actinides in solution at varying pH values
- Kinetic and thermodynamic studies on the adsorption of U(VI) ions on densely crosslinked poly(methacrylic acid) from aqueous solutions
- Extraction of americium(III) from nitric acid medium by CMPO-TBP extractants in ionic liquid diluent
- Uranium, plutonium and neptunium co-recovery with high nitric acid concentration in extraction section by simplified solvent extraction process
- Separation of 109Cd from silver targets by nanohematite
- An adapted purification procedure to improve the quality of 90Y for clinical use
- Novel polymer vectors of 64Cu
- Radiosynthesis of a novel potential adenosine A3 receptor ligand, 5-ethyl 2,4-diethyl-3-((2-[18F]fluoroethyl)sulfanylcarbonyl)-6-phenylpyridine-5-carboxylate ([18F]FE@SUPPY:2)
- Determination of solubility parameters of cobalt(II) and indium(III) oxinates by tracer technique
- Evaluation of trace elements in chewing tobacco and snuff using instrumental neutron activation analysis (INAA) and atomic absorption spectroscopy (AAS)
