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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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Fusion Science and Technology
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Latest News
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.
Mengkuo Wang, Timothy J. Tautges, Douglass L. Henderson, Laila El-Guebaly, Xueren Wang
Fusion Science and Technology | Volume 47 | Number 4 | May 2005 | Pages 1079-1083
Technical Paper | Fusion Energy - First Wall, Blanket, and Shield | doi.org/10.13182/FST05-A830
Articles are hosted by Taylor and Francis Online.
MCNPX's geometric modeling capabilities are limited to Boolean combinations of primitive geometric shapes. These capabilities are not sufficient for simulating particle transport in stellerators, whose geometric models are quite complex. We describe a CAD based implementation of MCNPX, where a CAD geometry engine is used directly for solid model representation and evaluation. The application of this code, to calculating the neutron wall loading distribution () in the Z and toroidal directions for the ARIES-CS design, is described.