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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.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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BREAKING NEWS: Trump issues executive orders to overhaul nuclear industry
The Trump administration issued four executive orders today aimed at boosting domestic nuclear deployment ahead of significant growth in projected energy demand in the coming decades.
During a live signing in the Oval Office, President Donald Trump called nuclear “a hot industry,” adding, “It’s a brilliant industry. [But] you’ve got to do it right. It’s become very safe and environmental.”
David Halabuk, Tomas Navrat
Nuclear Science and Engineering | Volume 189 | Number 1 | January 2018 | Pages 69-81
Technical Paper | doi.org/10.1080/00295639.2017.1373518
Articles are hosted by Taylor and Francis Online.
This paper presents a thermomechanical assessment of various types of fuel cladding during a reactivity-initiated accident (RIA) which is simulated by the finite element analysis program ANSYS. Four cladding concepts are analyzed; one concept considers currently used zirconium alloy and three concepts consider silicon carbide (SiC) material. The SiC claddings consist either of composite material or of a two-layered structure formed of SiC composite and monolithic SiC. Each cladding is analyzed for two states of nuclear fuel: fresh and high burnup. A gap that exists between fuel pellets and cladding in fresh state is either reduced or removed in a high burnup state. It was shown that zirconium cladding resists RIA conditions very well in fresh state, however, in high burnup state significant stress and plastic strain occur. The SiC cladding was shown to have many advantages over zirconium alloy. Nevertheless, its lower strength appears to be critical in RIA conditions when cladding needs to withstand exceeding loading after the fuel-cladding gap disappears due to the expansion of the fuel pellet.