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

D. Cerroni, A. Cervone, S.Manservisi, P. Meloni, M. Polidori (2014). Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop. ASME [10.1115/ICONE22-31052].

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

A. Cervone;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 (2014). Preliminary results on the coupling of a three-dimensional lead fast reactor model and a one-dimensional external loop. ASME [10.1115/ICONE22-31052].
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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