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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.
D. Rochman, A. J. Koning
Nuclear Science and Engineering | Volume 170 | Number 3 | March 2012 | Pages 265-279
Technical Paper | doi.org/10.13182/NSE11-37
Articles are hosted by Taylor and Francis Online.
This paper presents new evaluations for the two natural isotopes of copper from thermal neutron energy up to 200 MeV, including covariances. The evaluation and adjustment method consists of applying a Monte Carlo method to select the model parameters to obtain better agreement with differential data, criticality safety, and fusion benchmarks. In the resonance range, the latest resonance parameters and uncertainties are adopted. In the fast neutron range, the TALYS reaction code is used to calculate all nuclear data quantities and covariances. The proposed evaluations present important improvements for fusion benchmarks compared to the current libraries. These new evaluations of 63Cu and 65Cu are proposed for the JEFF-3.2 European nuclear data library. As a spinoff, correlations between cross sections and benchmarks can be obtained.