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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.
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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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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.
H. I. Liou, R. E. Chrien
Nuclear Science and Engineering | Volume 62 | Number 3 | March 1977 | Pages 463-478
Technical Paper | doi.org/10.13182/NSE77-A26985
Articles are hosted by Taylor and Francis Online.
Designers of thermal-neutron reactors have always had to adjust microscopic nuclear cross sections to predict neutron multiplication in slightly enriched uranium lattices. It has been surmised that the problem lies in an overestimation of the neutron capture cross section of 238U below 100 eV. We have measured these cross sections by three independent experiments. First, a series of neutron transmission and self-indication measurements were taken on samples of 238U ranging from 10.79 to 11 620 b/atom in inverse thickness. The level parameters were obtained using area analysis and multilevel fits. Next, the capture cross sections deduced from these level parameters were confirmed by direct measurements on both the continuum and discrete line portions of the low-energy gamma-ray spectra. High resolution measurements on the gamma-ray spectra were carried out from 530 to 900 keV over the neutron energy range from near thermal to ∼20 eV. Finally, a further check was made by activating thin samples of 238U with monochromatic neutrons obtained by Bragg scattering. The result is consistent with the capture cross sections obtained by the gamma-ray spectra measurement. Our results reduce, by 25%, the shielded capture integral discrepancy observed in early Bettis Atomic Power Laboratory critical experiments (TRX) with low-235U-enriched uranium rods latticed in water. When they are coupled with refined lattice calculations, much of the long-standing discrepancy is removed.