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Conference Spotlight
2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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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Researchers use one-of-a-kind expertise and capabilities to test fuels of tomorrow
At the Idaho National Laboratory Hot Fuel Examination Facility, containment box operator Jake Maupin moves a manipulator arm into position around a pencil-thin nuclear fuel rod. He is preparing for a procedure that he and his colleagues have practiced repeatedly in anticipation of this moment in the hot cell.
J. S. Hendricks, L. L. Carter
Nuclear Science and Engineering | Volume 77 | Number 1 | January 1981 | Pages 71-83
Technical Paper | doi.org/10.13182/NSE81-A21340
Articles are hosted by Taylor and Francis Online.
A calculational benchmark of neutron transport through a slab of iron is based on a rigorous Monte Carlo treatment of ENDF/B-IV and ENDF/B-V cross sections. The model consists of 2-, 14-, and 40-MeV neutrons incident on a 3-m infinite slab. This benchmark problem can be used to validate multigroup cross-section libraries and the associated multigroup transport codes. Plots and tables of the data show the spatial and energy distribution of neutrons for monoenergetic normally incident sources.
