ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Education, Training & Workforce Development
The Education, Training & Workforce Development Division provides communication among the academic, industrial, and governmental communities through the exchange of views and information on matters related to education, training and workforce development in nuclear and radiological science, engineering, and technology. Industry leaders, education and training professionals, and interested students work together through Society-sponsored meetings and publications, to enrich their professional development, to educate the general public, and to advance nuclear and radiological science and engineering.
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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Nuclear Technology
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May 2025
Latest News
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.
J. S. Hendricks, L. L. Carter
Nuclear Science and Engineering | Volume 77 | Number 1 | January 1981 | Pages 71-83
Technical Paper | doi.org/10.13182/NSE81-A21340
Articles are hosted by Taylor and Francis Online.
A calculational benchmark of neutron transport through a slab of iron is based on a rigorous Monte Carlo treatment of ENDF/B-IV and ENDF/B-V cross sections. The model consists of 2-, 14-, and 40-MeV neutrons incident on a 3-m infinite slab. This benchmark problem can be used to validate multigroup cross-section libraries and the associated multigroup transport codes. Plots and tables of the data show the spatial and energy distribution of neutrons for monoenergetic normally incident sources.
