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The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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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.
Y. Harima
Nuclear Science and Engineering | Volume 85 | Number 1 | September 1983 | Pages 45-51
Technical Note | doi.org/10.13182/NSE83-A17150
Articles are hosted by Taylor and Francis Online.
An empirical formula for gamma-ray buildup factors in two-layer shields is proposed. The values of the parameters are given for the formula when fitted to the dose buildup factors, calculated by the invariant imbedding method, for normally incident gamma rays penetrating two-layer shields comprised of combinations of water, iron, or lead slabs. The results from the present formula are in excellent agreement with the basic data in the 0.66- to 10-MeV energy range and for total thicknesses up to ∼20 mfp. The parameters used in the formula change smoothly with the source energy. Therefore; the buildup factor for any arbitrary energy can easily be estimated by interpolation of the parameters with respect to energy. The buildup factors provided by this formula also are in good agreement with those from transport calculations for two-layer shields consisting of water and lead. These factors also agree with those measured by two ionization chambers for 60Co radiation penetrating two-layer shields comprised of water, iron, or lead slabs.
