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2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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ANS Winter Meeting: What it will take to “Fuel our Nuclear Future"
The 2021 ANS Winter Meeting and Technology Expo began this morning with a Opening Plenary Session chaired by Winter Meeting general chair Amir Vexler, president and chief executive officer of Orano USA. It was an opportunity to both celebrate achievements that are already building a “Nuclear Future” and to identify needs and challenges ahead.
Influential speakers from the U.S. Congress, the Department of Energy, and the Nuclear Energy Institute joined ANS president Steven Nesbit and ANS CEO/executive director Craig Piercy to explore key issues associated with the front end of the nuclear fuel cycle, including supply and demand for high-assay, low-enriched uranium (HALEU). They didn’t stop there, however. They took questions from an in-person and virtual audience that probed other requirements of a sustainable nuclear future, including fueling a human resources pipeline.
A. Wysocki, A. Ward, A. Manera, T. Downar, Y. Xu, J. March-Leuba, C. Thurston, N. Hudson, A. Ireland
Nuclear Technology | Volume 190 | Number 3 | June 2015 | Pages 323-335
Technical Paper | Thermal Hydraulics | dx.doi.org/10.13182/NT14-79
Articles are hosted by Taylor and Francis Online.
The PATHS (PARCS Advanced Thermal Hydraulic Solver) code was developed at the University of Michigan in support of U.S. Nuclear Regulatory Commission research to solve the steady-state, two-phase, thermal-hydraulic equations for a boiling water reactor (BWR) and to provide thermal-hydraulic feedback for BWR depletion calculations with the neutronics code PARCS (Purdue Advanced Reactor Core Simulator). The simplified solution methodology, including a three-equation drift flux formulation and an optimized iteration scheme, yields very fast run times in comparison to conventional thermal-hydraulic systems codes used in the industry, while still retaining sufficient accuracy for applications such as BWR depletion calculations. The capability to model advanced BWR fuel designs with part-length fuel rods and heterogeneous axial channel flow geometry has been implemented in PATHS, and the code has been validated against previously benchmarked advanced core simulators as well as BWR plant and experimental data. The modifications to the codes and the results of the validation are described in this paper.