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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
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 THD
Wednesday, June 14, 2023|10:00–11:45AM EDT|Marriott 2
Session Chair:
Subash Sharma (Univ. Massachusetts, Lowell)
Alternate Chair:
Dillon R. Shaver (ANL)
Session Organizer:
Yassin A. Hassan
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A Stochastic Approach to Estimate Fission Product Retention in a Sodium Fast Reactor (SFR)
10:00–10:20AM EDT
Rohan Biwalkar (Pittsburgh Technical), Sola Talabi (Pittsburgh Technical)
Paper
PIV Measurements of Laminar Flow Through Porous Blocked Wire-Wrapped Subchannels
10:20–10:40AM EDT
Trevor Melsheimer (TAMU), Craig Menezes (TAMU), Dalton Pyle (TAMU), Matt Kinsky (TAMU), Yassin Hassan (TAMU), Kim Hansol (TAMU)
Design of a Liquid Sodium Corrosion Testing Facility
10:40–11:00AM EDT
Devin McCormick (Univ. Wisconsin, Madison), Ryder Belgarde (Univ. Wisconsin, Madison), Tiago A. Moreira (Univ. Wisconsin, Madison), Paul Brooks (Univ. Wisconsin, Madison), Mark Anderson (Univ. Wisconsin, Madison)
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