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

Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop

MANSERVISI, SANDRO;
2014

Abstract

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
2014
22nd International Conference on Nuclear Engineering
46
55
D. Cerroni; A. Cervone; S.Manservisi; P. Meloni; M. Polidori
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11585/383066
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