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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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Latest News
Feinstein Institutes to research novel radiation countermeasure
The Feinstein Institutes for Medical Research, home of the research institutes of New York’s Northwell Health, announced it has received a five-year, $2.9 million grant from the National Institutes of Health to investigate the potential of human ghrelin, a naturally occurring hormone, as a medical countermeasure against radiation-induced gastrointestinal syndrome (GI-ARS).
Suddhasattwa Ghosh, Krishan Kumar, Aligati Venkatesh, P. Venkatesh, Bandi Prabhakara Reddy
Nuclear Technology | Volume 195 | Number 3 | September 2016 | Pages 253-272
Technical Paper | doi.org/10.13182/NT16-37
Articles are hosted by Taylor and Francis Online.
The DIFAC (DIFfusion of Actinides in EleCtrorefiner) computer code for pyroprocessing, developed earlier by the authors, is modified in the present work to model electrorefining at the liquid cadmium electrode. The modeling of electrorefining of metal fuels requires accurate knowledge of two important kinetic parameters: exchange current density io and diffusion layer thickness δ. These are estimated in the present work by polarization methods and employing Tafel and Allen-Hickling analysis for Gd3+/Gd, U3+/U, and Zr2+/Zr couples in LiCl-KCl eutectic at 773 K for an inert cathode and compared with literature data, wherever possible. The equilibrium potentials for these couples at an inert electrode are found to be −1.94, −1.52, and −1.22 V, respectively, at 773 K. Electrochemical studies are also carried out in LiCl-KCl eutectic to estimate io and δ for the anodic dissolution of Na-bonded U-Zr and Gd-U-Zr alloy and are compared with the anodic dissolution of U-Pu-Zr alloy. The equilibrium potential of Na-bonded U-Zr alloy in LiCl-KCl-UCl3 was found to be −1.46 V, and those for Gd-U-Zr alloy in blank LiCl-KCl and LiCl-KCl-UCl3 were −1.56 and −1.34 V, respectively, at 773 K. The exchange current densities of Na-bonded U-Zr and Gd-U-Zr alloy were found to be in the range of 40.1 to 46.5 mA · cm−2 and 16.8 to 27.3 mA · cm−2 at 773 K, respectively.
A preliminary design of the liquid cadmium electrode suitable for laboratory-scale experiments on uranium- and plutonium-based systems is also reported in the present work. The io and δ of gadolinium, uranium, and zirconium are subsequently estimated at the liquid cadmium electrode at 773 K. The equilibrium potentials for Gd3+/Cd6Gd, U3+/[U]Cd, and Zr2+/Cd3Zr couples in LiCl-KCl eutectic at 773 K for the liquid cadmium electrode are found to be −1.35, −1.13, and−1.12 V, respectively. Finally, a few algorithms are proposed for modeling electrorefining data at the liquid cadmium electrode for multicomponent systems.