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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
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.
