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Division Spotlight
Mathematics & Computation
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.
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.
John R. Phillips
Nuclear Technology | Volume 28 | Number 2 | February 1976 | Pages 282-290
Technical Paper | Technique | doi.org/10.13182/NT76-A31569
Articles are hosted by Taylor and Francis Online.
The method for the nondestructive determination of two-dimensional radial isotopic distributions of fission and activation products of irradiated fuel pins was improved. In this method the fuel pins are gamma-scanned diametrally at two or more angular orientations, and the diametral isotopic scans are unfolded into two-dimensional radial isotopic distributions. The computer code for processing the data was improved so that it calculates the individual diametral volume segments, the source self-attenuation factors, and the source intensity matrices. The two-dimensional source intensity matrices are presented as radial isotopic distributions, density plots, contour plots, and isometric projections. The new computer code improves the precision and reduces the analysis time as shown in the examination of more than 10 experimental fast-reactor fuel pins.
