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Conference Spotlight
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.
Seong-Youn Kim, Raphael Aronson
Nuclear Science and Engineering | Volume 73 | Number 1 | January 1980 | Pages 56-65
Technical Paper | doi.org/10.13182/NSE80-A18708
Articles are hosted by Taylor and Francis Online.
The transfer matrix method is used to solve the Milne problem for a half space for neutrons interacting with a moderator at temperature T. Two different scattering models are considered. They are (a) the free monatomic gas of arbitrary molecular mass with constant cross sections in the center-of-mass system, and (b) the Nelkin kernel for water. Both models permit an additional 1/v absorption cross section. We have obtained accurate numerical values for the diffusion length, the extrapolated end point, the critical absorption strength, and the boundary heating for a variety of values of the parameters. Comparison is made both with other calculations and with experiments.