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Aerospace Nuclear Science & Technology
Organized to promote the advancement of knowledge in the use of nuclear science and technologies in the aerospace application. Specialized nuclear-based technologies and applications are needed to advance the state-of-the-art in aerospace design, engineering and operations to explore planetary bodies in our solar system and beyond, plus enhance the safety of air travel, especially high speed air travel. Areas of interest will include but are not limited to the creation of nuclear-based power and propulsion systems, multifunctional materials to protect humans and electronic components from atmospheric, space, and nuclear power system radiation, human factor strategies for the safety and reliable operation of nuclear power and propulsion plants by non-specialized personnel and more.
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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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Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
Osvaldo Fiorella, Manlio Mangia, Elio Oliveri
Nuclear Technology | Volume 61 | Number 2 | May 1983 | Pages 353-361
Technical Paper | Second International RETRAN Meeting / Radioisotopes and Isotope | doi.org/10.13182/NT83-A33203
Articles are hosted by Taylor and Francis Online.
Optimal step assays and interstage up-flow rates for enriching and stripping sections of uranium gaseous diffusion squared-off cascades are manageably determined without any additional approximations beyond the usual ones (i.e., a close separation process and a constant cut in the whole section). This is accomplished by the application of the optimization conditions to the function to be minimized, i.e., the total up-flow rate, still expressed in integral form. The use of suitable dimensionless variables allows quick evaluations of the optimal parameters of any plant, provided that the product and waste assays range from 1 to 99% and from 0.05 to 0.65%, respectively, and that the number of enriching and stripping steps be, at most, seven and four, respectively. The results are consistent with those available in the literature; in particular, it is confirmed that, for low and intermediate product assays, a number of enriching steps higher than five is unnecessary in most cases.