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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.
R. Pepelnik, H. U. Fanger, W. Michaelis
Nuclear Science and Engineering | Volume 106 | Number 3 | November 1990 | Pages 243-248
Technical Paper | doi.org/10.13182/NSE90-A29053
Articles are hosted by Taylor and Francis Online.
A sealed-tube, high-current, low-energy accelerator (190 kV, 150 mA) in operation at the GKSS Research Center since 1981 is described. The deuterium-tritium reaction yields a total source strength of 3 × 1012 n/s. The neutron flux in the center of the hollow cylinder target is ∼3 × 1010 n/cm2·s in a 4-cm3 volume. Numerous 14-MeV neutron reaction cross sections have been determined with satisfactory accuracy; however, the system has been mainly used for neutron activation analysis. To predict the gamma-ray activity of any element after short-term irradiation with 14-MeV neutrons, a sensitivity study was performed, which proved to be a useful tool for analyzing complex spectra.