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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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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.
J. S. Hendricks, L. L. Carter
Nuclear Science and Engineering | Volume 89 | Number 2 | February 1985 | Pages 118-130
Technical Paper | doi.org/10.13182/NSE85-A18186
Articles are hosted by Taylor and Francis Online.
A synergistic method is described for the angle biasing of anisotropic scattering kernels in Monte Carlo calculations. The method generalizes Dwivedi's suggestion of using the exponential transform to cancel the undesirable fluctuations of angle biasing. Only photons are examined because the biasing of the Klein-Nishina scattering kernel can be treated analytically in contrast to more general neutron scattering kernels, which would require a numerical treatment. Three-dimensional continuous-energy results indicate that angle biasing in conjunction with the exponential transform is better than either by itself and greatly enhances Monte Carlo transport for the cases shown.