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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
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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Apr 2025
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
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.
International High-Level Radioactive Waste Management Conference
Plenary Session|Panel
Thursday, November 17, 2022|3:15–5:00PM MST|Mesquite
Session Chairs:
Robert Joseph (INL)
Sylvia Saltzstein (Sandia)
PANELISTS
Bob LedouxARPA-E
Kim PetryDOE:NE
Monica C RegalbutoINL
Sven BaderOrano
Doug Ammerman SNL
Ethan Bates Deep Isolation
The management of advanced reactor waste and HALEU fuels will have some similarities to managing SNF from the current LWR fleet, but the new form factors and uranium assays will also require nuanced adjustments to cask designs, certifications, and disposal requirements. It will likely be prudent to identify these differences as early as possible so that accommodations can be made for the differences. This panel will also discuss what changes might be necessary to the existing infrastructure and what is being done to prepare for future storage, shipments, and disposal.
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