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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
H. T. Hahn, E. M. Vander Wall
Nuclear Science and Engineering | Volume 17 | Number 4 | December 1963 | Pages 613-619
Technical Paper | doi.org/10.13182/NSE63-A18453
Articles are hosted by Taylor and Francis Online.
The behavior was studied of dibutyl phosphoric acid (HDBP) and its complexes in the uranium stripping and tributyl phosphate (TBP) scrubbing operations. The solubilizing effect of TBP upon UO2(DBP)2 is shown. At low concentrations of nitric acid and TBP, UO2(DBP)2 has greater solubility in the aqueous phase. For enriched uranium stripping conditions, the solubility ratio is almost unity, and DBP may partially accompany uranium through the stripping step. The partition of uranium between TBP-Amsco and dilute nitric acid solutions is shown as a function of both HDBP and TBP concentrations. In the region of interest, uranium appears to be extracted as a complex with DBP/U ratio of one. As the DBP/U ratio increases from one to two, solid UO2(DBP)2 appears. Above a ratio of two, and in the presence of TBP, no solids remained after equilibration, indicating additional DBP-TBP complex formation. For the succeeding TBP scrubbing operation, the TBP distribution coefficient between Amsco and aqueous phase is 290. However, pilot plant experiments were unsuccessful in scrubbing to the desired phosphate level due to two effects. Laboratory studies indicated an equilibration time of two minutes, considerably longer than permitted in the pilot plant tests. The presence of an aqueous-favoring phosphorus species was also established. The latter can be removed by absorption on a hydrated zirconium oxide column and the column regenerated with NaOH. The absorption behavior of HDBP and a plant evaporator phosphate contaminant are compared.