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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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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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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.
Steven E. Aumeier, John C. Lee, Derek M. Cribley, William R. Martin
Nuclear Technology | Volume 108 | Number 3 | December 1994 | Pages 299-319
Technical Paper | Fission Reactor | doi.org/10.13182/NT94-A35014
Articles are hosted by Taylor and Francis Online.
We present a new time-based cross-section parameterization scheme that allows for a more accurate global depletion analysis than current methodologies without requiring major modifications to existing codes. The new cross-section parameterization scheme makes use of few-group macroscopic cross sections calculated as a function of time at several different power levels. These cross sections are block ordered by time rather than exposure to allow for the explicit representation of instantaneous control, i.e., soluble boron concentration, and thus accurate isotopic history, within the base cross-section library. The scheme is applied to a global depletion analysis of the Slightly Enriched Spectral-Shift Reactor, an advanced converter reactor based on a pressurized water reactor design, using the CPM-2 assembly-level collision probability code and the UM2DB two-dimensional diffusion code. The depletion calculation establishes the feasibility and potential advantages of the proposed cross-section parameterization methodology and shows that through a judicious choice of spectral shift control rod withdrawal strategies, it is possible to substantially increase fuel resource utilization via the spectral shift effect while maintaining acceptable power peaking factors.
