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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver 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
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
K. Shure
Nuclear Science and Engineering | Volume 85 | Number 1 | September 1983 | Pages 51-55
Technical Note | doi.org/10.13182/NSE83-A17151
Articles are hosted by Taylor and Francis Online.
The contributions from actinides to the decay heat and the decay rate relative to those from fission products in highly irradiated 235U-enriched uranium has been assessed. This assessment, which is based on measured and associated calculated actinide concentrations in a sample of uranium in which the 235U had been burned to 17% of its original >97% content (i.e., to ∼17% 235U), indicates that for most practical times (<108 s) after reactor shutdown, the actinide contribution to the decay heat and to the decay rate is a reasonably small fraction (<7%) of the total and comes mainly from 237U, 238Np, and 238Pu. These results differ from those for uranium only slightly enriched in 235U.
