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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
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!
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Apr 2025
Jan 2025
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Nuclear Science and Engineering
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
18th International Probabilistic Safety Assessment and Analysis (PSA 2023)
Technical Session|PSA Analyses: Methods and Applications
Thursday, July 20, 2023|8:00–9:30AM EDT|300A
Session Chair:
Michelle Bensi (University of Maryland)
Alternate Chair:
Michael D. Muhlheim
Session Organizer:
Askin Guler Yigitoglu (ORNL)
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Probabilistic Risk Assessment of a Light-Water Reactor Coupled with a High-Temperature Electrolysis Hydrogen Production Plant
8:00–8:25AM EDT
Robby Christian (INL), Courtney Otani (INL), Kurt Vedros (INL), Austin M. Glover (Sandia)
Paper
Risk-Informed Design Process of Emergency Core Cooling System in the Floating Nuclear Power Plants
8:25–8:50AM EDT
Changhong Peng (Univ. Science and Technology of China), Xinyan Xu (Univ. Science and Technology of China), Lanxin Gong (Univ. Science and Technology of China)
PACE Level 3 PSA Code -- Developments to Account for Radiosensitivity Dependence on Age and Sex of Health Effects and Impact of High Spatial and Temporal Resolution Population Estimates
8:50–9:15AM EDT
Thomas Charnock (United Kingdom Health Security Agency), Kelly Jones (United Kingdom Health Security Agency), Antony Bexon (United Kingdom Health Security Agency)
Application of Probabilistic Safety Assessment Within an Integrated Safety Approach for Re-Design of the Nuclear Island During Post-Operational Phase
9:15–9:40AM EDT
Filip Van Opstal (Tractebel ENGIE), Federico Agosti (Tractebel ENGIE)
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