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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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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.
F. Schmittroth, R. E. Schenter
Nuclear Science and Engineering | Volume 74 | Number 3 | June 1980 | Pages 168-177
Technical Paper | doi.org/10.13182/NSE80-A20116
Articles are hosted by Taylor and Francis Online.
A method of cross-section adjustment and evaluation is presented. Based on a finite element representation, the method is especially appropriate for cross sections that are well represented by continuous functions. It is also suitable for many problems outside the area of cross-section evaluation where one desires to fit curves that have complicated shapes not easily described by low-order polynomials. The algorithm is based on least-squares techniques that use complete covariance information and prior values. Nuclear model calculations, microscopic and integral data, and the results of prior multigroup adjustments can be combined in a single consistent evaluation. Results are presented for an illustrative example and for the evaluation of the 54Fe(n, p) dosimeter cross section.