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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.
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.
J. B. Czirr, G. S. Sidhu
Nuclear Science and Engineering | Volume 60 | Number 4 | August 1976 | Pages 383-389
Technical Paper | doi.org/10.13182/NSE76-A26899
Articles are hosted by Taylor and Francis Online.
We have measured the ratio of the 235U fission cross section to the 6Li(n, α) cross section at neutron energies from thermal to 680 keV. The Lawrence Livermore Laboratory electron Linac provided a pulsed source of neutrons, and energies were measured by time-o f-flight. The evaluated 6Li cross section was used to obtain σ(n, f) for 235U from 100 eV to 680 keV and to normalize the results to the accepted thermal fission cross-section value.