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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.
T. Duracz, R. Zelazny
Nuclear Science and Engineering | Volume 84 | Number 2 | June 1983 | Pages 164-166
Technical Note | doi.org/10.13182/NSE83-A17723
Articles are hosted by Taylor and Francis Online.
A systematic approach to the problem of defining effective scattering cross sections for neutron diffusion equations is presented. In our analysis, anisotropic scattering of the second order is assumed for the one-speed transport equation, and criterion of preserving both the diffusion length and the total absorption serves as a basis for the derivation of effective isotropic scattering cross sections for both transport and diffusion equations.
