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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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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.
Thomas E. Sampson
Nuclear Science and Engineering | Volume 54 | Number 4 | August 1974 | Pages 470-474
Technical Note | doi.org/10.13182/NSE54-470
Articles are hosted by Taylor and Francis Online.
Neutron yields in UF6 arising from the 19F(α, n)22Na reaction and spontaneous fission of 238U are reported. Passive neutron counting in nearly 4π geometry was used to measure the absolute yields from eight small UF6 samples of varying isotopic composition. The specific yields for 234U and 238U are in excellent agreement with values calculated from thick target excitation functions for fluorine. The values of the specific yield from the four uranium isotopes are also in reasonable agreement with recent measurements utilizing a similar technique.