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Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
William G. Davey
Nuclear Science and Engineering | Volume 26 | Number 2 | October 1966 | Pages 149-169
Technical Paper | doi.org/10.13182/NSE66-A28158
Articles are hosted by Taylor and Francis Online.
The published cross sections of 232Th, 233U, 234U, 235U, 236U, 237Np, 238U, 239Pu, 240Pu, 241Pu, and 242Pu from 1 keV to 10 MeV have been carefully studied to select best cross sections for fast reactor analysis. Frequently, the measurement is not of the absolute cross section but of the ratio between the unknown and some reference cross section; thus, in comparing measurements, it is important to determine if the same reference data were used in all cases. In this study, emphasis has been placed on determining the reference data used and, where necessary, the published data have been revised to accord with more accurate, currently accepted cross sections. Thus, it is believed that a consistent set of cross-section data has been derived. Some cross checks have been made by comparing calculations based on the selected cross sections with integral measurements in broad fast-neutron spectra. The study shows the great importance of the 235U fission cross section in deriving other cross sections and emphasizes the necessity of re-evaluating nearly all fission cross sections, if it proves necessary to revise the 235U data.