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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
Meeting Spotlight
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
Standards Program
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.
C. J. Jackson, D. G. Cacuci, H. B. Finnemann
Nuclear Science and Engineering | Volume 131 | Number 2 | February 1999 | Pages 143-163
Technical Paper | doi.org/10.13182/NSE99-A2025
Articles are hosted by Taylor and Francis Online.
A dimensionally adaptive, automatic switching algorithm has been developed for the RELAP5/PANBOX coupled thermal-hydraulics and neutron kinetics system to switch between three-dimensional (3-D), one-dimensional (1-D), and point neutron kinetics models during a transient calculation. The 3-D, 1-D, and point neutron kinetics models are developed and analyzed. The basis of this development is the consistent and stable nodal expansion method. The 1-D and point neutron kinetics models are derived in a unified manner from the 3-D model using the adiabatic approximation. The operator formulation of perturbation/sensitivity theory is consistently used to determine the reactivity for the point-kinetics model. Furthermore, the new features of the coupled RELAP5/PANBOX code are described. This provides the basis underlying the dimensionally adaptive algorithm.
