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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.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Daniele Tomatis
Nuclear Science and Engineering | Volume 193 | Number 6 | June 2019 | Pages 622-637
Technical Paper | doi.org/10.1080/00295639.2018.1553428
Articles are hosted by Taylor and Francis Online.
The cross section preparation for reactor calculations produces few-group data libraries whose storage needs in memory increase severely when more physical output is requested. As a matter of fact, depletion chains with many isotopes are suggested for a more accurate isotopic inventory all along the fuel cycle, and coarse meshes are not suitable to compute finer distributions of reaction rates in highly heterogeneous systems. This work investigates the use of compression techniques on the power form factors to evaluate potential storage reduction for homogenized pin-by-pin data. The form factors are analyzed in several physical conditions of normal operation for Gd-poisoned UO2 and mixed-oxide fuel assemblies whose specifications come from a benchmark problem. Two numerical transforms are studied on two different applications, providing recommendations for general use in core calculations.