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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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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
Jun 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
July 2025
Nuclear Technology
Fusion Science and Technology
Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
Technical Session|New and Advanced Reactors
Tuesday, August 22, 2023|1:30–3:10PM EDT|Columbia 2
Session Chair:
Mauricio Tano (INL)
Alternate Chair:
Lambert Fick (Kairos Power)
Session Organizer:
Rui Hu
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Development and First Application of a Simplified Tool for the Design of a Molten Salt Reactor
1:30–1:50PM EDT
E. Martin Lopez (CEA), L. Matteo (CEA), V. Pascal (CEA), M. Mascaron (CEA), A. Petrilli (CEA)
Paper
Transient Modeling and Simulation of a Generic Stable Salt Reactor
1:50–2:10PM EDT
Thanh Hua (ANL), Yan Cao (ANL), Rui Hu (ANL), Andrew Ballard (Moltex Energy Canada), David Catalan (Moltex Energy Canada)
Benchmarking MSRE Reactivity Insertion Tests Using SPECTRA and SAM
2:10–2:30PM EDT
Marek Stempniewicz (Nuclear Research & Consultancy Group), Ferry Roelofs (Nuclear Research & Consultancy Group), Ting Fei (ANL), Thanh Hua (ANL), Bo Feng (ANL), Rui Hu (ANL)
Simulations to Understand Thermal Performance of Helically Rifled Heat Transfer Enhancements for Molten Salts
2:30–2:50PM EDT
James R. Vulcanoff (Virginia Commonwealth Univ.), Ryan P. McGuire (Virginia Commonwealth Univ.), Lane B. Carasik (Virginia Commonwealth Univ.)
Implementation of a Gas Transport Model in SAM for Modeling Molten Salt Reactors
2:50–3:10PM EDT
Robert Salko (ORNL), Travis Mui (ANL), Rui Hu (ANL), Ling Zou (ANL)
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