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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
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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.
K. V. Subbaiah, A. Natarajan
Nuclear Science and Engineering | Volume 96 | Number 4 | August 1987 | Pages 330-342
Technical Paper | doi.org/10.13182/NSE87-A16396
Articles are hosted by Taylor and Francis Online.
Transport calculations have been performed using the one-dimensional gamma-ray transport code ASFIT for materials of high atomic number (Z), such as tin, tungsten, lead, and uranium, for incident energies in the range of 0.030 to 0.5 MeV, where the fluorescent X rays are important. The relative impact of different components of K X rays on the spectra and buildup factors at various depths in the medium has been assessed for a typical case. Approximate analytic results are derived and compared with the computed X-ray contributions. Point isotropic air and medium response buildup factors computed for these materials have been given, filling the gap in the existing standard tables. Since the buildup factors are not amenable for conventional interpolation in this region, the values are given at close intervals of incident photon energy.