ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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!
Latest Magazine Issues
Mar 2025
Jan 2025
Latest Journal Issues
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 THD
Tuesday, November 15, 2022|10:00–11:45AM MST|Sonoran 3
Session Chair:
Donna P. Guillen (INL)
Session Organizer:
Alternate Chairs:
Piyush Sabharwall (INL)
Brian G. Woods (Oregon State)
Panelists will present the experimental capabilities of test facilities that can be used to support the development of new reactor concepts and designs. These facilities will have the ability to generate high-quality data that can be used for system and computational fluid dynamic code validation. Such data can support safety analyses and reduce uncertainty, especially for thermal hydraulic phenomena of interest, enhance our technical understanding, and fill in technical gaps. The panelists will also provide information on the current status and on future testing that is being planned. The presentations include: Thermal Hydraulic Testing Facilities for Lead Fast Reactor Development; Developing Nuclear Technology through Design-Build-Test; High Pressure/High Temperature Helium Flow Test Facility at City College of New York; and Combined Positron Emission Particle Tracking/CT Experimental Capabilities for Nuclear Engineering Applications.
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