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Division Spotlight
Fusion Energy
This division promotes the development and timely introduction of fusion energy as a sustainable energy source with favorable economic, environmental, and safety attributes. The division cooperates with other organizations on common issues of multidisciplinary fusion science and technology, conducts professional meetings, and disseminates technical information in support of these goals. Members focus on the assessment and resolution of critical developmental issues for practical fusion energy applications.
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.
J. H. Marable, C. R. Weisbin, G. de Saussure
Nuclear Science and Engineering | Volume 75 | Number 1 | July 1980 | Pages 30-55
Technical Paper | doi.org/10.13182/NSE80-A20316
Articles are hosted by Taylor and Francis Online.
Using an extensive data base of sensitivities and evaluated covariances, this work incorporates 11 fast-reactor benchmark experiments and 2 neutron-field benchmark experiments into the adjustment of a 26-group cross-section library based primarily on Evaluated Nuclear Data File (ENDF)/B-IV. The covariance data include correlations between cross sections for different energies, reactions, and materials, and between integral experiments, and covariances of calculational bias factors due to specific modeling and calculational procedures. The adjustments of the group cross sections are examined in some detail and are smaller than the estimated standard deviations. The results of the adjustment are applied to the determination of the uncertainties in the multiplication factor and in the breeding ratio of a large liquid-metal fast breeder reactor design model fixed by the Large Core Code Evaluation Working Group. For this static model the adjustment procedure reduces the calculated uncertainty in keff from 3.1% to 0.5% and in breeding ratio for the critical reactor from 3.5% to 1.9%.