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Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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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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.
Roberto Orsi
Nuclear Science and Engineering | Volume 154 | Number 2 | October 2006 | Pages 247-259
Computer Code Abstract | doi.org/10.13182/NSE06-A2631
Articles are hosted by Taylor and Francis Online.
The finite difference approach poses a major problem of keeping the exact values of material zone areas and volumes in any geometric simulation for transport calculations. When this requirement is not thoroughly fulfilled, updating density values may be necessary to conserve material zone masses. A method is described that conserves the mass of geometrically complex material zones simulated on both Cartesian and cylindrical mesh grids and its implementation in BOT3P5.0, which is the latest version of the BOT3P code package, publicly and freely available from the Organization for Economic Cooperation and Development/Nuclear Energy Agency Data Bank. BOT3P5.0 lets users optionally require as refined a computation as desired of the possible area and volume error of material zones due to the stair-cased geometry representation and automatically corrects material densities to globally conserve masses. BOT3P5.0 optionally stores on binary outputs the detailed material zone distribution map inside each cell of the mesh grid according to a submesh grid refinement defined in input by the user and the area and volume fraction distribution of the different material zones contained in meshes at zone interfaces. That also allows a local (per-cell) density correction as an alternative to the approach of a uniform density correction on the whole zone domain and makes it possible to perform material zone homogenization locally and transport analyses more accurately.