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Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Proving DRACO will deliver
The United States is now closer than it has been in over five decades to launching the first nuclear thermal rocket into space, thanks to DRACO—the Demonstration Rocket for Agile Cislunar Orbit.
Rajesh Ahluwalia, Thanh Q. Hua, Howard K. Geyer
Nuclear Technology | Volume 126 | Number 3 | June 1999 | Pages 289-302
Technical Paper | Reprocessing | doi.org/10.13182/NT99-A2975
Articles are hosted by Taylor and Francis Online.
A theoretical model is used to analyze the transport of U and Zr in electrorefining of irradiated binary Experimental Breeder Reactor-II fuel. A limiting-current hypothesis is advanced to explain the observed dissolution of Zr in the presence of U at high, intermediate, and low cell voltages. The internal diffusion model predicts the existence of a critical current and a critical voltage for Zr oxidation. Experimental results are presented for a test designed and run based on optimum conditions determined from the model to dissolve U expediently while retaining Zr in the anode baskets. A simple model of kinetic exchange reactions between salt-phase U and Cd-phase Zr is formulated to explain the measured electrodeposition of Zr on the solid cathode. It is shown that the Zr content of the deposit is overpredicted if the pool is considered isolated and grossly underpredicted if the salt phase is equilibrated instantaneously with the Cd pool. Finally, the aspects of anodic current efficiency and cathodic collection efficiency are discussed taking into account shorting between the dissolution baskets and the Cd pool, multiple oxidation states of Zr, and the exchange reactions between the fuel and UCl3 prior to electrotransport.