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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.
G. Ronald Dalton
Nuclear Science and Engineering | Volume 13 | Number 2 | June 1962 | Pages 190-196
Technical Paper | doi.org/10.13182/NSE62-A26147
Articles are hosted by Taylor and Francis Online.
The time and speed independent neutron transport equation in its integral form is applied to the calculation of the disturbed neutron flux in the vicinity of neutron detectors. The method is also applied to the calculation of the average flux in a two-detector system where the detectors are close enough to interact with each other. Hand methods of solving the integral equations are developed and shown to give results in good agreement with more accurate numerical methods of solving the integral equations.