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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Latest News
ARG-US Remote Monitoring Systems: Use Cases and Applications in Nuclear Facilities and During Transportation
As highlighted in the Spring 2024 issue of Radwaste Solutions, researchers at the Department of Energy’s Argonne National Laboratory are developing and deploying ARG-US—meaning “Watchful Guardian”—remote monitoring systems technologies to enhance the safety, security, and safeguards (3S) of packages of nuclear and other radioactive material during storage, transportation, and disposal.
M. J. Rivard, B. L. Kirk, L. C. Leal
Nuclear Science and Engineering | Volume 149 | Number 1 | January 2005 | Pages 101-106
Technical Paper | doi.org/10.13182/NSE05-A2480
Articles are hosted by Taylor and Francis Online.
Radiation dose distributions of brachytherapy sources are generally characterized with the assumption that all internal components are equally radioactive. Autoradiographs and discussions with source manufacturers indicated this assumption of the radionuclide physical distribution may be invalid. Consequently, clinical dose distributions would be in error when not accounting for these internal variations. Many implants use brachytherapy sources with four 125I resin beads and two radiopaque markers used for imaging. Monte Carlo methods were used to determine dose contributions from each of the resin beads. These contributions were compared with those from an idealized source having a uniform physical distribution. Upon varying the 125I physical distribution while retaining the same overall radioactivity, the dose distribution along the transverse plane remained constant within 5% for r > 0.5 cm. For r 0.5 cm, relative positioning of the resin beads dominated the shielding effects, and dose distributions varied up to a factor of 3 at r = 0.05 cm. For points off the transverse plane, comparisons of the uniform and nonuniform dose distributions produced larger variations. Shielding effects within the capsule were virtually constant along the source long axis and demonstrated that anisotropy variations among the four resin beads were dependent on internal component positioning.