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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
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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