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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.
Toshimasa Miura
Nuclear Science and Engineering | Volume 102 | Number 2 | June 1989 | Pages 191-209
Technical Paper | doi.org/10.13182/NSE89-A23643
Articles are hosted by Taylor and Francis Online.
Empirical formulas are derived that describe neutron flux distributions in straight and bent cylindrical steel-walled ducts in symmetrical and asymmetrical geometries. Asymmetry is defined by the slant angle between the duct axis and a line passing through the center of the duct mouth and source. Streaming neutrons are divided into direct, albedo, and penetration components. The first two components are described by a function of the axial distance in units of the square root of the line-of-sight area. The last component is described by a function of the neutron flux distribution in the shield in the absence of the duct. Formulas are applicable to thermal, epithermal, intermediate, and fast neutrons, respectively, in the following range: (a) duct diameter is 5 to 20 cm, (b) duct length is up to 240 cm, (c) slant angle is 0 to 90 deg, (d) steel wall thickness is 0 to 1.0 cm, (e) bent angle is 45 to 90 deg, and (f) surrounding medium of the duct is water or ordinary concrete. Calculations by formulas agree with experimental data, in general, within an accuracy of ±30%.