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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Mar 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
Technical Session|Sponsored by RPD|Cosponsored by OPD
Wednesday, June 10, 2020|4:35–6:20PM EDT
Session Chair:
Abdalla Abou Jaoude (INL)
Session Organizers:
Pavel V. Tsvetkov (LANL)
Jeffrey C. King (Colorado School of Mines)
John Bess (INL)
Alternate Chairs:
Track Organizer:
Staff Producer:
Jessica Vazquez (American Nuclear Society)
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Depletion Analysis of a Micro-Reactor Annular Heat Pipe Fuel Element
Subash Sharma (Univ. of Massachusetts Lowell), Stephanie Astudillo-Gomez (Univ. of Massachusetts Lowell), Alec Golas (Univ. of Massachusetts Lowell)
Paper
MINI-SMR-21 in Once-through Long-lived Fuel Cycle Feasibility Assessment
Gray Chang (JFoster and Associates), James Harrell (Co-Author), Julie Foster (JFoster & Associates, LLC)
A Numerical Tool for Space Nuclear Reactor Design based on Molten Salt Reactors (MSRs)
V. Richard (Université Grenoble-Alpes), Franco Quinteros (University Grenoble-Alpes), J. Giraud (Université Grenoble-Alpes), V. Ghetta (Université Grenoble-Alpes), J. Blanco (Université Grenoble-Alpes), M. Tano (Texas A&M Univ.), P. Rubiolo (Université Grenoble-Alpes)
Optimal Sizing of a Micro-Reactor for Embedded Grid Systems
Kathryn D. Huff (Univ. of Illinois, Urbana-Champaign), Samuel G. Dotson (Univ. of Illinois, Urbana-Champaign)
Presentation Video (Visible to Attendees)
Advanced Nuclear Engineering to Support Space Exploration
Yoichi Momozaki (ANL), Florent Heidet (ANL)
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