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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
Standards Program
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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How to talk about nuclear
In your career as a professional in the nuclear community, chances are you will, at some point, be asked (or volunteer) to talk to at least one layperson about the technology you know and love. You might even be asked to present to a whole group of nonnuclear folks, perhaps as a pitch to some company tangential to your company’s business. So, without further ado, let me give you some pointers on the best way to approach this important and surprisingly complicated task.
Stephen M. Goldberg, Manson Benedict, Hans W. Levi
Nuclear Science and Engineering | Volume 47 | Number 2 | February 1972 | Pages 169-186
Technical Paper | doi.org/10.13182/NSE72-A22394
Articles are hosted by Taylor and Francis Online.
Equations, tables, and charts are given which represent the equilibrium distribution of uranyl nitrate and nitric acid between aqueous solution and an organic phase consisting of 30 vol% tributyl phosphate (TBP) in a hydrocarbon diluent at 25°C. These should be useful for prediction of distribution equilibria in the Purex solvent extraction process for recovering uranium from irradiated nuclear fuel. Equations for the aqueous phase represent the activities of water, nitric acid, and uranyl nitrate hexahydrate as functions of the molality of the last two components. These equations were developed by correlating data for the partial pressure of nitric acid over aqueous solutions of nitric acid and uranyl nitrate. Distribution equilibrium data for uranyl nitrate are correlated by an equation representing the ratio of the activity coefficient of the uranyl nitrate-TBP complex to the activity coefficient of uncomplexed TBP as a function of the uranyl nitrate and nitric acid content of the organic phase. This equation was fitted to distribution data for uranyl nitrate observed in the presence of nitric acid and in the absence of nitric acid. The observed molality of uranyl nitrate in the organic phase agrees with the molality predicted by this equation within an average deviation of 5.8%. Distribution equilibrium data for nitric acid in the presence of uranyl nitrate were correlated in analogous fashion.