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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
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
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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