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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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!
Latest Magazine Issues
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
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.
Technical Session|Sponsored by Materials Science & Technology
Friday, April 15, 2022|1:15–2:45PM CDT|Loyalty Room
Sponsored by ANS Material Science & Technology Division
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Evaluation of Kanthal APMT as Potential Fuel Cladding Material
Arnold Pradhan (Univ. of Idaho)
Paper
Characterization of High Temperature Surrogate Cermet Fuel for Nuclear Thermal Propulsion (NTP)
James F. Mudd (Missouri Univ. Science and Technology)
Design Analysis of Accident-tolerant Cladding FeCrAl for Light Water Reactors
Rowan Marchie (Univ. Michigan), Henry Blackwood (Univ. Michigan), Jonathan Kurian (Univ. Michigan), Fei Gao (Univ. Michigan), Lumin Wang (Univ. Michigan)
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