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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Masahiro Nabeshima
Nuclear Technology | Volume 93 | Number 3 | March 1991 | Pages 362-374
Technical Paper | Enrichment and Reprocessing System | doi.org/10.13182/NT91-A34530
Articles are hosted by Taylor and Francis Online.
The hydrodynamic characteristics of pulsed columns fitted with perforated sieve or baffle-plate internals are investigated experimentally using a Purex H2O-HNO3-U(VI)-30% tri-n-butylphosphate/dodecane liquid system. A set of semiempirical equations for axial mixing, mean diameter, and settling velocity of the droplets is derived from the experimental results and incorporated into the DYNAC computer simulation program to predict fluid flow behavior in pulsed columns. Various hydrodynamic parameters are studied in detail, and the code is demonstrated to be satisfactory in analyzing the residence behavior of fluids and the extractive mass transfer of uranium in normal and transient operations.