An accurate three-dimensional simulation of all the components of the primary circuit of a LFR (Lead Fast Reactor) cannot be performed with the current computational power. One strategy to deal with such complex systems is to adopt a multi-scale approach, where different models and geometric representations are introduced for different parts of the reactor. This paper presents a preliminary assessment of a methodology developed in the framework of the FEM-LCORE code to simulate an accident scenario where natural circulation plays a key role in the heat removal.
- Nuclear Engineering Division
Preliminary Results on the Coupling of a Three-Dimensional Lead Fast Reactor Model and a One-Dimensional External Loop
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Cerroni, D, Cervone, A, Meloni, P, Polidori, M, & Manservisi, S. "Preliminary Results on the Coupling of a Three-Dimensional Lead Fast Reactor Model and a One-Dimensional External Loop." Proceedings of the 2014 22nd International Conference on Nuclear Engineering. Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory. Prague, Czech Republic. July 7–11, 2014. V004T10A046. ASME. https://doi.org/10.1115/ICONE22-31052
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