ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
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
2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott 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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Jun 2025
Jan 2025
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Nuclear Science and Engineering
July 2025
Nuclear Technology
June 2025
Fusion Science and Technology
Latest News
Former NRC commissioners lend support to efforts to eliminate mandatory hearings
A group of nine former nuclear regulatory commissioners sent a letter Wednesday to the current Nuclear Regulatory Commission members lending support to efforts to get rid of mandatory hearings in the licensing process, which should speed up the process by three to six months and save millions of dollars.
Sunday, June 12, 2022|2:00–5:00PM PDT
Avila B
Summary Paragraph: UNF-ST&DARDS is being developed to provide the ability to perform automated analysis of spent fuel storage and transportation systems. One of the key capabilities of UNF-ST&DARDS is to perform criticality analysis of dry casks. UNF-ST&DARDS allows for modelling the variation of cask payload burnup enrichments and cooling times through a flexible GUI. Users can also modify, neutron absorber loadings, water soluble boron concentrations, and fuel and canister dimensions for fresh and spent fuel. This demonstration will show users how to perform criticality analysis for casks using templates and graphical user interface. Attendees have no requirements to watch the demonstrate, however, an RSICC license for UNF-ST&DARDS and SCALE is necessary if they would like to follow along.
