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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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Mar 2025
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Nuclear Science and Engineering
May 2025
Nuclear Technology
April 2025
Fusion Science and Technology
Latest News
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
Technical Session|Panel|Sponsored by RPD
Monday, November 13, 2023|1:00–2:45PM EST|Lincoln West
Session Chair:
John Jackson (INL)
Alternate Chair:
Abdalla Abou-Jaoude (INL)
Session Organizer:
As MARVEL completes its 90% final design, this panel session will provide a deep dive into the intricacies of the reactor demonstration. This session will specifically revolve around the final system configuration, fuel performance evaluation, validation of thermal hydraulics using an experimental facility, instrumentation and controls, and the detailed construction for the reactor. The fuel performance presentation will delve into some of the characteristics of the MARVEL TRIGA-based fuel and its associated behavior under various operational scenarios, within the basis of current fuel qualification. The results from the PCAT experimental test facilities that is intended to validate the natural circulation behavior within MARVEL will be discussed. This will be followed by an overview of the MARVEL instrumentation and controls, including the core reactivity control systems. Lastly, the detailed planned construction and assembly blueprint for the reactor within the TREAT facility will be presented.
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