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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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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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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.
A. Hébert
Nuclear Science and Engineering | Volume 160 | Number 2 | October 2008 | Pages 261-266
Technical Note | doi.org/10.13182/NSE160-261TN
Articles are hosted by Taylor and Francis Online.
The double-heterogeneity treatment is available in many lattice codes to represent the effect of one or many stochastic media on the deterministic solution of the neutron transport equation. A stochastic medium is a mixture of a diluent matrix with cylindrical or spherical microstructures of different sizes. Different models have been presented in the past, some limited to the collision probability method and others limited to the method of characteristics. We have reformulated these existing models in a uniform framework and introduced a scattering reduction, making them compatible with any solution technique of the neutron transport equation. This new approach has been implemented in the Dragon Version4 lattice code in a generic way that is interoperable with the overall code features. This approach can easily be implemented within any existing code dedicated to the solution of the transport equation.