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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.
Kenny C. Gross, Chris Passerello
Nuclear Science and Engineering | Volume 75 | Number 1 | July 1980 | Pages 1-11
Technical Paper | doi.org/10.13182/NSE80-A20313
Articles are hosted by Taylor and Francis Online.
A problem with the gas-tagging scheme for identification of failed fuel assemblies in fast and light water reactors (LWRs) may arise when elements in two or more assemblies fail simultaneously. One method recently developed for resolving multiple failures can identify a second, third, or fourth leaker, provided the compositions of the tags coming from the previous leakers have already been determined. For a commercial-sized fast reactor or an LWR, it may not be possible to determine the composition of each tag individually as the failures occur This paper describes the development of an analytical technique that is capable of resolving simultaneous fuel failures and can be applied even when none of the compositions of the previously leaked tags is known.