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
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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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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|Sponsored by RPD
Wednesday, June 10, 2020|2:30–4:15PM EDT
Session Chair:
Moussa Mahgerefteh (Exelon Corporation)
Alternate Chair:
Pavel Tsvetkov (LANL)
Session Organizer:
Track Organizer:
Staff Producer:
Jessica Vazquez (American Nuclear Society)
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Analytic Treatment of Intra-Fuel-Rod Temperature Distributions in the GPU-Based Continuous Energy Monte Carlo Code PRAGMA
Namjae Choi (Seoul Nat'l Univ.), Han Gyu Joo (Seoul Nat'l Univ.)
Paper
Presentation Video (Visible to Attendees)
Presentation Video
The Application of the Backward Differentiation Formula on the Transient Coupling of Three-dimensional Neutron Kinetics and Thermal Hydraulic
Yun Cai (Nuclear Power Institute of China), Xingjie Peng (Nuclear Power Institute of China), Qing Li (Nuclear Power Institute of China), Yingrui Yu (Nuclear Power Institute of China), Rui Guo (Nuclear Power Institute of China)
Adjoint Driven Ex-Core Response Estimation in PWR with Thermal Feedback
Shane C. Henderson (ORNL), Tara M. Pandya (ORNL), Shane Stimpson (ORNL)
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