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Division Spotlight
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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.
Yaqi Wang, Jean Ragusa
Nuclear Science and Engineering | Volume 161 | Number 1 | January 2009 | Pages 22-48
Technical Paper | doi.org/10.13182/NSE161-22
Articles are hosted by Taylor and Francis Online.
This paper presents fully automated hp-mesh refinement strategies applied to diffusion equations. In hp strategies, both the mesh size and the polynomial order can vary locally. Numerical results show that exponential convergence rates are achieved for a fraction of the number of unknowns needed with uniform refinement and h-adaptive strategies. The treatment of adaptivity in the multigroup case and the derivation of goal-oriented estimators for neutronics calculations are described. The smoothness of the multigroup components can vary greatly as a function of the energy group; this fact called for the development of group-dependent adapted spatial meshes. The goal-oriented process combines the standard hp adaptation technique with a goal-oriented adaptivity based on the simultaneous solution of an adjoint problem in order to compute quantities of interest, such as reaction rates in subdomains and pointwise fluxes or currents. These algorithms are tested for various multigroup one-dimensional and two-dimensional diffusion problems, and the numerical results confirm the exponential convergence rates predicted theoretically.