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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!
Latest Magazine Issues
Apr 2025
Jan 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.
Advances in Thermal Hydraulics (ATH 2022)
Technical Session
Tuesday, June 14, 2022|10:15AM–12:00PM PDT|Palos Verdes A/B
Session Chair:
Emilian Popov (ORNL)
Alternate Chairs:
Robert Martin (BWXT)
Session Organizer:
W. David Pointer
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The Effect of Cooling Efficiency on the Startup Characteristic and Performance of the Sodium Heat Pipes for the Special Purpose Reactor with Different Filling Ratio
Pei-Hsun Huang (Univ. Michigan), Taehwan Ahn (Univ. Michigan), Annalisa Manera (Univ. Michigan), Victor Petrov (Univ. Michigan)
Paper
Effects of Operational Conditions on the Geyser Boiling in the Sodium Heat Pipe for the Special Purpose Reactor
Taehwan Ahn (Univ. Michigan), Pei-Hsun Huang (Univ. Michigan), Annalisa Manera (Univ. Michigan), Victor Petrov (Univ. Michigan)
Preliminary Design and Analysis of Free-Piston Stirling Engines
Phat Doan (Univ. New Mexico), Minghui Chen (Univ. New Mexico)
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