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Division Spotlight
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.
Meeting Spotlight
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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Latest News
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.
Lakshmi Rangaswamy, L. S. Kothari, Feroz Ahmed
Nuclear Science and Engineering | Volume 59 | Number 3 | March 1976 | Pages 261-270
Technical Paper | doi.org/10.13182/NSE76-A26824
Articles are hosted by Taylor and Francis Online.
For one-speed neutrons, we have investigated the effect of anisotropy in the scattering kernel on their angular distribution at various space points inside slabs of different thicknesses. This has been done by solving the one-speed space-angle-dependent neutron transport equation for a pulsed source, by numerically iterating over the space and angle variables. We find that the fundamental decay constant decreases with increasing anisotropy, the effect being more in thicker slabs. The effect of scattering anisotropy on the angular flux inside slabs, as well as on leakage flux, has been reported. For a specific scattering kernel, the variation of angular flux with thickness of the slab is also discussed. Some of these results have been compared with those based on P1 and P3 approximations.