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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
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
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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 Advanced Reactors
Friday, April 15, 2022|9:45–11:15AM CDT|Excellence Room
Sponsored by
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A Method for Bubble Detection in Molten Salts using an Acoustic Resonator
Hayden S. Bland (NCSU), Matthew W. Field (NCSU), Christopher Williams (NCSU Department of Nuclear Engineering), Miranda Moultrie (NCSU Department of Nuclear Engineering)
Paper
Study of Bypass Flow in Prismatic Core Using One-Twelfth of the HTGR Core
Harish Aryal (University of Texas of the Permian Basin), Bishal Lamichhane (The University of Texas of Permian Basin)
Uranium Core Design for the Versatile Test Reactor
Andrew Taylor (NCSU), Anna Isom (NCSU), Jordan Page (NCSU), Jamison Harris (NCSU), Saoud Henzab (NCSU), Scott Palmtag (NCSU)
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