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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.
Yousef M. Farawila, Douglas W. Pruitt
Nuclear Science and Engineering | Volume 154 | Number 3 | November 2006 | Pages 316-327
Technical Paper | doi.org/10.13182/NSE06-A2636
Articles are hosted by Taylor and Francis Online.
A study of the nonlinear behavior of growing density-wave oscillations is presented in the framework of a reduced-order model. Nonlinear effects are included in both the hydraulic and neutron kinetics equations, where both were found to contribute to the observed limit cycles. In Part I of this paper, the basic concepts were developed and applied to the global oscillation mode where only the fundamental neutron flux mode excitation is considered. Approximate analytical solutions for the limit cycle amplitude and the time evolution of the transient were derived. In this paper, Part II, the model order is increased to allow the representation of the azimuthal neutron flux harmonic and the simulation of growing regional mode oscillations. Analysis demonstrates that the regional mode, unlike the global mode, may not always reach a stable limit cycle, and if it does, the regional limit cycle amplitudes are large compared with the global mode. An extended reduced-order model has been developed for use as an accurate quantitative tool for simulating actual reactor situations, whereas the current paradigm restricts the applicability of reduced-order models to gaining qualitative insights.