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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.
Peter Jacob, Herwig G. Paretzke
Nuclear Science and Engineering | Volume 93 | Number 3 | July 1986 | Pages 248-261
Technical Paper | doi.org/10.13182/NSE86-A17754
Articles are hosted by Taylor and Francis Online.
Exposure at 1 m above the ground from isotropic gamma-ray point sources in the soil has been studied by the Monte Carlo method for source energies from 40 keV to 5 MeV. Source depths from 0.1 down to 30 cm and horizontal distances out to 5 mfp have been considered. Considerable deviations were found in the results of different buildup factor methods since such methods do not account for geometric effects at the interface. Moreover, exposures from infinite and finite plane sources have been calculated. It is shown that, for source energies <662 keV, the buildup factor methods underestimate the kerma considerably. It is shown how surface roughness conditions can be accounted for by the introduction of an effective source depth in the soil. The validity of approximations used to describe the exposure from finite or inhomogeneous plane sources with values for infinite homogeneous plane sources was examined.