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Division Spotlight
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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NEA panel on AI hosted at World Governments Summit
A panel on the potential of artificial intelligence to accelerate small modular reactors was held at the World Governments Summit (WGS) in February in Dubai, United Arab Emirates. The OECD Nuclear Energy Agency cohosted the event, which attracted leaders from developers, IT companies, regulators, and other experts.
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%.