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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
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.
The Consortium for Advanced Simulation of Light Water Reactors Virtual Meeting
Technical Session|Panel|Sponsored by Fuel Materials and Chemistry
Thursday, November 19, 2020|10:00–11:45AM EST
Session Chair:
David Andersson (LANL)
Alternate Chair:
David J. Kropaczek
Track Organizer:
Scott P. Palmtag (NC State Univ.)
Staff Producer:
Brian Andersen (ORNL)
Several of the challenge problems in CASL required accurate nuclear fuel performance modeling capabilities for their solution, especially Pellet-Clad-Interaction (PCI) and Loss-of-Coolant-Accident (LOCA)/Reactivity-Insertions Accident (RIA). In order to address these challenge problems, CASL contributed to the development of the Bison fuel performance code and made significant investments in both capabilities and validation needed for the two challenge problems referenced above. In addition, CASL played a key role in developing Bison capabilities for Accident Tolerant Fuels (ATFs). Fuel performance modeling is closely tied to the underlying materials models. In several cases, CASL sought better models using multi-scale materials modeling and simulation techniques, which are particularly important for ATF concepts where experimental data is scarce. This panel session will discuss materials and nuclear fuel performance modeling performed in CASL. It will highlight historical perspectives, accomplishments, lessons-learned and remaining challenges.
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Materials and Fuel Performance Modeling History and Future Needs
David Andersson (Los Alamos National Laboratory), Joseph Y.R. Rashid (Structural Integrity Associates, Inc.), Chris Stanek (Los Alamos National Laboratory), Brian D. Wirth (University of Tennessee Knoxville), Jason Hales (Idaho National Laboratory), Richard L. Williamson (Idaho National Laboratory)
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