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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.
Utility Working Conference and Vendor Technology Expo (UWC 2022)
August 7–10, 2022
Marco Island, FL|JW Marriott Marco Island
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
Fusion Science and Technology
Carbon value: Lifetime extensions of nuclear reactors could save billions in climate mitigation costs
On the road to achieving net-zero by midcentury, low- or no-carbon energy sources that slash carbon dioxide emissions are critical weapons. Nevertheless, the role of nuclear energy—the single largest source of carbon-free electricity—remains uncertain.
Nuclear energy, which provides 20 percent of the electricity in the United States, has been a constant, reliable, carbon-free source for nearly 50 years. But our fleet of nuclear reactors is aging, with more than half of the 92 operating reactors across 29 states at or over 40 years old—the length of the original operating licenses issued to the power plants. While some reactors have been retired prematurely, there are two options for those that remain: retire them or renew their license.
Thursday, May 19, 2022|3:30–5:15PM EDT|Haselton
Vince Wang (U. of Utah)
Petri Guimaraes (Studsvik Scandpower)
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Boundary Condition Free Homogenization and Evaluation of its Performance in Fast Reactor Core Analysis
Shuhei Maruyama (Japan Atomic Energy Agency)
Presentation Video — Boundary Condition Free Homogenization and Evaluation of its performance in Fast Reactor Core Analysis
Flux Flattening Heavy Water Reactors with Accelerator-Driven Photoneutron Source
Arief Rahman Hakim (Ulsan Nat'l Institute of Science and Technology), Douglas A. Fynan (Ulsan Nat'l Institute of Science and Technology)
Enhancement Concept Reactor Physics Studies to Support HFIR Upgrade Planning Activities
D. Chandler (ORNL), C.D. Bryan (ORNL), J. L. McDuffee (ORNL)
Depletion Perturbation Theory: A Sensitivity Tool for the High Flux Reactor Conversion to Low Enriched Uranium
Davide Portinari (Institut Laue Langevin), Yoann Calzavara (Institute Laue Langevin), Laurent Chabert (TechnicAtome), Adrien Bidaud (LPSC-IN2P3-CNRS)
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