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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.
A. Hébert, G. Mathonnière
Nuclear Science and Engineering | Volume 115 | Number 2 | October 1993 | Pages 129-141
Technical Paper | doi.org/10.13182/NSE115-129
Articles are hosted by Taylor and Francis Online.
Proposals are made for improving current second-generation superhomogénéisation (SPH) methods in three different ways and to use them in heterogeneous and homogeneous diffusion procedures for reactor design and operating calculations. The first improvement consists of using a surface radial leakage model in the flux calculation to represent the macroscopic flux curvature in the assembly. The second improvement is accomplished by the introduction of the Selengut normalization in the SPH equivalence procedure replacing the flux-volume normalization currently used with second-generation methods. Finally, the buckling calculation is improved to better represent the target color-set. Second- and third-generation SPH techniques for heterogeneous or homogeneous diffusion procedures are now implemented as a unified algorithm in a lattice code. Two-group benchmarks are proposed to measure precisely the equivalence effectiveness and the improvement gained with third-generation methods.