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Featured researches published by M. Angelucci.


Science and Technology of Nuclear Installations | 2017

STH-CFD Codes Coupled Calculations Applied to HLM Loop and Pool Systems

M. Angelucci; Daniele Martelli; G. Barone; I. Di Piazza; Nicola Forgione

This work describes the coupling methodology between a modified version of RELAP5/Mod3.3 and ANSYS Fluent CFD code developed at the University of Pisa. The described coupling procedure can be classified as “two-way,” nonoverlapping, “online” coupling. In this work, a semi-implicit numerical scheme has been implemented, giving greater stability to the simulations. A MATLAB script manages both the codes, oversees the reading and writing of the boundary conditions at the interfaces, and handles the exchange of data. A new tool was used to control the Fluent session, allowing a reduction of the time required for the exchange of data. The coupling tool was used to simulate a loop system (NACIE facility) and a pool system (CIRCE facility), both working with Lead Bismuth Eutectic and located at ENEA Brasimone Research Centre. Some modifications in the coupling procedure turned out to be necessary to apply the methodology in the pool system. In this paper, the comparison between the obtained coupled numerical results and the experimental data is presented. The good agreement between experiments and calculations evinces the capability of the coupled calculation to model correctly the involved phenomena.


Volume 5: High-Pressure Technology; ASME NDE Division; 22nd Scavuzzo Student Paper Symposium and Competition | 2014

Experimental and Numerical Analysis for Fluid-Structure Interaction for an Enclosed Hexagonal Assembly

Lucia Sargentini; Benjamin Cariteau; M. Angelucci

This paper is related to fluid-structure interaction analysis of sodium cooled fast reactors core (Na-FBR). Sudden liquid evacuation between assemblies could lead to overall core movements (flowering and compaction) causing variations of core reactivity. The comprehension of the structure behavior during the evacuation could improve the knowledge about some SCRAMs for negative reactivity occurred in PHENIX reactor and could contribute on the study of the dynamic behavior of a FBR core. An experimental facility (PISE-2c) is designed composed by a Poly-methyl methacrylate hexagonal rods (2D-plan similitude with PHENIX assembly) with a very thin gap between assemblies. Another experimental device (PISE-1a) is designed and composed by a single hexagonal rod for testing the dynamic characteristics. Different experiments are envisaged: free vibrations and oscillations during water injection.A phenomenological analysis is reported showing the flow behavior in the gap and the structure response. Also computational simulations are presented in this paper. An efficient numerical method is used to solve Navier-Stokes equations coupled with structure dynamic equation. The numerical method is verified by the comparison of analytic models and experiments.Copyright


Nuclear Engineering and Design | 2016

Heat transfer on HLM cooled wire-spaced fuel pin bundle simulator in the NACIE-UP facility

Ivan Di Piazza; M. Angelucci; R. Marinari; Mariano Tarantino; Nicola Forgione


Nuclear Engineering and Design | 2013

Numerical estimation of wall friction ratio near the pseudo-critical point with CFD-models

M. Angelucci; Walter Ambrosini; Nicola Forgione


Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance | 2018

Post-Test CFD Analysis of Non-Uniformly Heated 19-Pin Fuel Bundle Cooled by HLM

R. Marinari; I. Di Piazza; M. Angelucci; Daniele Martelli


Volume 6B: Thermal-Hydraulics and Safety Analyses | 2018

Thermal Hydraulic Analysis of the CIRCE-HERO Pool-Type Facility

Bruno Gonfiotti; G. Barone; M. Angelucci; Daniele Martelli; Nicola Forgione; Alessandro Del Nevo; Mariano Tarantino


Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues | 2018

Experimental Tests With Non-Uniformly Heated 19-Pins Fuel Bundle Cooled by HLM

M. Angelucci; I. Di Piazza; Mariano Tarantino; R. Marinari; G. Polazzi; V. Sermenghi


Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation | 2018

Blind Simulations of NACIE-UP Experimental Tests by STH Codes

Nicola Forgione; M. Angelucci; G. Barone; Massimiliano Polidori; A. Cervone; Ivan Di Piazza; Fabio Giannetti; Pierdomenico Lorusso; Thorsten Hollands; Angel Papukchiev


Progress in Nuclear Energy | 2018

In-loop oxygen reduction in HLM thermal-hydraulic facility NACIE-UP

Serena Bassini; I. Di Piazza; Andrea Antonelli; M. Angelucci; V. Sermenghi; G. Polazzi; Mariano Tarantino


Nuclear Engineering and Design | 2018

Experimental campaign on the HLM loop NACIE-UP with instrumented wire-spaced fuel pin simulator

M. Angelucci; Ivan Di Piazza; Daniele Martelli

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