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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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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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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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Survey says . . . Emotional intelligence important in nuclear industry
The American Nuclear Society’s Diversity and Inclusion in ANS (DIA) Committee hosted a workshop social at the 2024 Winter Conference & Expo in November that brought dozens of attendees together for an engaging—and educational—twist on the game show Family Feud.
Frederick R. Best, Michael J. Driscoll
Nuclear Technology | Volume 73 | Number 1 | April 1986 | Pages 55-68
Technical Paper | Fuel Cycle | doi.org/10.13182/NT86-A16201
Articles are hosted by Taylor and Francis Online.
A computer program entitled URPE (Uranium Recovery Performance and Economics) has been developed to simulate the engineering performance and provide an economic analysis of a plant recovering uranium from seawater. The conceptual system design used as the focal point for the more general analysis consists of a floating oil-rig type of platform single-point moored in an open ocean current, using either high-volume-low-head axial pumps or the velocity head of the ambient ocean current to force seawater through a mass transfer medium [hydrous titanium oxide (HTO) coated onto particle beds or stacked tubes]. Uranium is recovered from the seawater by an adsorption process, and later eluted from the adsorber by an ammonium carbonate solution. A multiproduct cogenerating plant on board the platform burns coal to raise steam for electricity generation, desalination, and process heat requirements. Scrubbed stack gas from the plant is processed to recover carbon dioxide for chemical make-up needs. The equilibrium isotherm and the diffusion constant for the uranyl-HTO system, which are needed for bed performance calculations, have been calculated based on the data reported in the literature. In addition, a technique for calculating the rate constant of a fixed-bed adsorbing system has been developed for use with Thomas’ solution for predicting fixed-bed performance. The URPE program has been benchmarked against the results of previous studies by Oak Ridge National Laboratory and Exxon, and found to make comparable performance and economic estimates when applied under the same set of ground rules. The URPE code was then used in an extensive series of parametric and sensitivity studies to identify optimum bed-operating conditions and important areas for future research and development (R&D). The program showed that thin beds of small, thinly coated particles were the preferred bed configuration and that actively pumped systems outperform current-driven units. Based on the URPE analysis, the minimum expected cost of uranium recovered from seawater would be no lower than $316/lb U3O8 for adsorber material having a capacity equal to 210 mg U/kg Ti, but might be reduced to $150/lb U3O8 if at least a fourfold increase in adsorption capacity could be achieved. Specific R&D objectives other than increasing particle capacity are also identified. Prospects are considered to be sufficiently good to warrant recommending further work.