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Division Spotlight
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.
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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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.
John F. Geldard, Adolph L. Beyerlein, Houn-Lin Chiu
Nuclear Technology | Volume 78 | Number 2 | August 1987 | Pages 151-156
Technical Paper | Chemical Processing | doi.org/10.13182/NT87-A33993
Articles are hosted by Taylor and Francis Online.
The mathematical basis for a computer code PUNE (Plutonium-Uranium-Non-Equilibrium) is described. The code simulates the steady-state concentration profiles of solvent extraction contactors used in the Purex process under conditions where material transfer between phases deviates from the equilibrium limit. The deviation is accounted for by a mass transfer area characteristic of the operating conditions of a contactor, and a mass transfer coefficient for the chemical species of interest. In the limit of infinite mass transfer rate, PUNE gives the same results as other codes that calculate equilibrium profiles. For 1A and IE contactors, the computational times are reduced between two- and fivefold over times required by other codes that generate the steady-state profiles via transient state conditions. For 1B or partitioning contactors, the reduction in time can be more than 20-fold. Since there is no loss of accuracy in these calculations, PUNE represents an important advance in the determination of steady-state profiles, especially for 1B contactors because it is with these that the greatest computational difficulties are encountered.