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Division Spotlight
Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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|Sponsored by RPD
Wednesday, November 16, 2022|3:15–5:00PM MST|Sonoran 7
Session Chair:
Friederike Bostelmann (ORNL)
Alternate Chair:
Pavel V. Tsvetkov
Session Organizer:
Massimiliano Fratoni (UC Berkeley)
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JOYO Benchmark Evaluation of the Advanced Reactor Modeling Interface
3:15–3:35PM MST
Michael Huang (TerraPower), Barry Mingst (TerraPower), Zhiwen Xu (TerraPower)
Paper
Size-Dependent Neutronic Optimization of Ultra-Long-Life Molten Salt and Metal Reactors (MSMR)
3:35–3:55PM MST
Eunhyug Lee (KAIST), Taesuk Oh (KAIST), Seongdong Jang (KAERI), Yonghee Kim (KAIST)
A Study on Control Algorithm for Daily Load-Follow Operation in the APR1400 Reactor
3:55–4:15PM MST
Husam Khalefih (KAIST), Yonghee Kim (KAIST)
A Method for Critical Control System Configuration Search when Using Monte Carlo Neutronics Codes
4:15–4:35PM MST
Dean Price (Univ. Michigan), Nathan Roskoff (Westinghouse Electric Co.)
Highlights of Neutronics Analyses for the Pre-Conceptual NIST Neutron Source Design
4:35–4:55PM MST
Osman S. Celikten (NIST Center for Neutron Research), Dagistan Sahin (NIST Center for Neutron Research), Abdullah G. Weiss (NIST Center for Neutron Research)
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