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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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|Computational Fluid Dynamics and Thermal Hydraulics
Wednesday, April 30, 2025|1:00–2:40PM MDT|Horace Tabor
Session Chair:
Mauricio Tano (INL)
Alternate Chair:
Guillaume Giudicelli (INL)
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A Direct Forcing Immersed Boundary Technique Developed in the NekRS Spectral Element CFD Solver
1:00–1:25PM MDT
Aya Hegazy (Univ. Illinois, Urbana-Champaign), April Novak (Univ. Illinois, Urbana-Champaign), Rizwan Uddin (Univ. Illinois, Urbana-Champaign)
Paper
Thermal Feedback Models for Microreactor Core Simulations
1:25–1:50PM MDT
Benjamin Collins (Veracity Nuclear), Micah Best (Veracity Nuclear), Aaron Graham (Veracity Nuclear)
Analysis of Fluid Flow Benchmarks for Single-Phase Liquids Using SyTH
1:50–2:15PM MDT
Austin Skiba (Univ. Texas, Austin), Nicholas Herring (Univ. Texas, Austin), Caleb Miller (Univ. Texas, Austin), Benjamin Collins (Univ. Texas, Austin), Kevin Clarno (Univ. Texas, Austin)
Implementation and Analysis of Delayed Neutron and Decay Heat Precursor Transport in the SyTH Model for Molten Salt Reactor Applications
2:15–2:40PM MDT
Braden Pecora (Univ. Texas, Austin), Benjamin S. Collins (Univ. Texas, Austin), Cole Gentry (Univ. Texas, Austin), Nicholas Herring (Univ. Texas, Austin), Kevin Clarno (Univ. Texas, Austin)
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