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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
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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Latest News
Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
James Corson, Alice Chung, Steven Muller
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 261-268
Research Article | doi.org/10.1080/00295450.2023.2181042
Articles are hosted by Taylor and Francis Online.
This paper presents the Fuel Analysis under Steady-state and Transient (FAST) code contribution to the P2M Simulation Exercise on past fuel melting irradiation experiments organized within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency’s Framework for Irradiated Experiments (FIDES). The benchmark consists of comparisons to two power ramps (xM-3 and HBC-4) that experienced fuel centerline melting. In general, FAST accurately captured the behavior of the fuel rods during the tests, though there are some notable discrepancies between the FAST results and the cladding elongation and fission gas release during the xM-3 power ramp.
