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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
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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May 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Countering the nuclear workforce shortage narrative
James Chamberlain, director of the Nuclear, Utilities, and Energy Sector at Rullion, has declared that the nuclear industry will not have workforce challenges going forward. “It’s time to challenge the scarcity narrative,” he wrote in a recent online article. “Nuclear isn't short of talent; it’s short of imagination in how it attracts, trains, and supports the workforce of the future.”
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.
