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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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
June 2025
Nuclear Technology
May 2025
Fusion Science and Technology
Latest News
EnergySolutions to help explore advanced reactor development in Utah
Utah-based waste management company EnergySolutions announced that it has signed a memorandum of understating with the Intermountain Power Agency and the state of Utah to explore the development of advanced nuclear power generation at the Intermountain Power Project (IPP) site near Delta, Utah.
Technical Session|Sponsored by RPD
Tuesday, November 19, 2024|10:00–11:45AM EST|Biscayne 2
Session Chair:
Carlo Fiorina (TAMU)
Alternate Chair:
Stefano Terlizzi (Penn State)
Session Organizer:
Zeyun Wu (Virginia Commonwealth Univ.)
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Selection of Reload Fuel TRU Fraction for Online Refueling of Waste-Burning Stable Salt Reactor
10:00–10:20AM EST
Seungug Jae (Univ. Michigan), Won Sik Yang (Univ. Michigan), Thanh Hua (ANL), Yan Cao (ANL)
Paper
Effect of Turbulent Diffusion on Delayed Neutron Precursors in the Molten Salt Reactor Experiment (MSRE)
10:20–10:40AM EST
Mohamed H. Elhareef (Virginia Commonwealth Univ.), Zeyun Wu (Virginia Commonwealth Univ.)
Dynamic Analysis of the Molten Salt Reactor Experiment (MSRE) Using Uranium-233 Fuel Salt: A Multi-Physics Simulation Approach
10:40–11:00AM EST
Faisal A. Alseaidan (Univ. California, Berkeley), Tatiana Siaraferas (Univ. California, Berkeley), Massimiliano Fratoni (Univ. California, Berkeley)
Coupled Neutronics -- Thermal-Hydraulics -- Thermomechanics Modeling of Molten Chloride Reactor
11:00–11:20AM EST
Mauricio Tano (INL), Ramiro Freile (INL), Rodrigo de Oliveira (INL), Samuel A. Walker (INL), Abdalla Abou-Jaoude (INL)
Impact of Heaters on Molten Salt Reactor Dynamics
11:20–11:40AM EST
Thabit Abuqudaira (TAMU), Pavel Tsvetkov (TAMU), Piyush Sabharwall (INL)
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