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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
Materials in Nuclear Energy Systems (MiNES 2023)
December 10–14, 2023
New Orleans, LA|New Orleans Marriott
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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Eisenhower’s “Atoms for Peace” at 70
Seventy years ago to the day, President Dwight D. Eisenhower gave his historic address to the United Nations General Assembly in New York City. (See December 2023 Nuclear News's “Leaders” column to read the reflections of Kathryn Huff, the Department of Energy’s assistant secretary for nuclear energy, on the speech’s anniversary.)
W. Van Snyder
Nuclear Technology | Volume 208 | Number 9 | September 2022 | Pages 1416-1432
Technical Paper | doi.org/10.1080/00295450.2021.2024023
Articles are hosted by Taylor and Francis Online.
A new form for metallic nuclear reactor fuel is proposed consisting of finely divided particles (tens of micrometers) mixed with sodium for thermal bond. Fuel pins filled with this form of fuel would have greater fuel density than with solid slugs fabricated at 75% smear density. Greater fuel density reduces enrichment requirements for initial fuel loading. A larger surface-to-volume ratio allows more fission product gases and metallic fission products to diffuse out of fuel particles, resulting in less swelling, greater burnup before processing, and simple preliminary thermomechanical spent fuel processing steps that might be used several times before the more expensive pyroelectric process develolped for the Experimental Breeder Reactor II (EBR-II). Less frequent pyroelectric processing, simple preliminary processing, and a larger surface-to-volume ratio reduce total processing cost. Preliminary processing produces separate fission products, in particular cesium and strontium, in metallic rather than salt or mineral form, thereby simplifying and reducing storage cost. Intrinsically structurally weak fuel would not rupture fuel pin cladding by swelling. The expense and complexity of the process would be offset by reduced total system cost.