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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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University of Nebraska–Lincoln: Home of ANS’s newest student section
Following official confirmation in June at the American Nuclear Society’s 2025 Annual Conference, the University of Nebraska–Lincoln has kicked off its first year as the newest ANS student section.
James Corson, Alice Chung, Steven Muller
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 261-268
Research Article | doi.org/10.1080/00295450.2023.2181042
Articles are hosted by Taylor and Francis Online.
This paper presents the Fuel Analysis under Steady-state and Transient (FAST) code contribution to the P2M Simulation Exercise on past fuel melting irradiation experiments organized within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency’s Framework for Irradiated Experiments (FIDES). The benchmark consists of comparisons to two power ramps (xM-3 and HBC-4) that experienced fuel centerline melting. In general, FAST accurately captured the behavior of the fuel rods during the tests, though there are some notable discrepancies between the FAST results and the cladding elongation and fission gas release during the xM-3 power ramp.
