In this thesis it is shown the development, implementation and numerical solution of several computational fluid dynamics models for the study of liquid metal flows. The work is organized in two main parts in which different modeling techniques are analyzed. These two parts are introduced by a brief chapter on the finite element methods and on the computational platform developed during the Ph.D. studies which have been the basis for the implementation and numerical solution of all the developed mathematical models. In the first part, turbulence modeling based on Reynolds Averaged Navier Stokes equations is considered for the study of turbulent heat transfer in liquid metal flows. A new four parameter turbulence model is introduced and validated in two different k-e and k-w formulations. Several results in four geometries interesting for the fast nuclear reactor field are reported in order to assess and prove the feasibility of this model for the study of turbulent heat transfer in liquid metal flows. In the second part the adjoint optimal control theory is introduced. Some numerical cases are presented by solving the optimality system with state and adjoint variables. The first application is a temperature boundary optimal control in which an improved way of setting boundary conditions in weak form has been developed. The second application is a distributed optimal control problem for the RANS system. Numerical simulations in two and three dimensions have been carried on for this type of applications and are reported in the final chapter.

In recent years numerical simulations are becoming fundamental for the design of many engineering components. For this reason many multiphysical and multiscale problems are investigated by coupling different existent software created specifically for solving each single problem. However, because of the intrinsic differences among these codes, such coupling is very challenging. In this thesis we develop a computational platform that can be used to integrate different computing tools into the common framework of the SALOME platform. Inside this platform various codes are coupled through numerical libraries with the purpose of exchanging data and melting intrinsic differences. After a description of the generic code integration procedure into the numerical platform, we introduce three classes of problems where different codes have been coupled and complex computational problems are studied. In the irst problem class, the computational platform is used to study a nuclear reactor system. We study the dynamics of a multiscale primary loop of a liquid metal reactor by coupling a mono-dimensional system code with the high resolution three-dimensional full scale core components models. Also we investigate a thermal-hydraulic-neutron multiphysics problem. The heat energy production in the reactor core, obtained by solving the neutron code DRAGON-DONJON, is coupled with the solution of the thermal-hydraulics conservative equations implemented in a in-house code. In the second problem class, we consider multiscale multiphysics Fluid Structure Interaction problems implemented in different modules of the FEMUs code. The mechanics of a three-dimensional particular component of the cardiovascular system is coupled with a mono-dimensional model that takes into account the remaining parts of a simplified circulatory system. Finally, in the last class of problems, Multiphase Fluid tructure Interaction problems are investigated by coupling the solution of a multiphase fluid interface advection VOF module with a FSI solver.

Many energetic and environmental evaluations need appropriate meteorological data, as input to analysis and prevision softwares. In Italy there aren't adeguate meteorological data because, in many cases, they are incomplete, incorrect and also very expensive for a long-term analysis (that needs multi-year data sets). A possible solution to this problem is the use of a Typical Meteorological Year (TRY), generated for specific applications. Nowadays the TRYs have been created, using statistical criteria, just for the analysis of solar energy systems and for predicting the thermal performance of buildings, applying it also to the study of photovoltaic plants (PV), though not specifically created for this type of application. The present research has defined the methodology for the creation of TRYs for different applications. In particular TRYs for environmental and wind plant analysis have been created. This is the innovative aspect of this research, never explored before. In additions, the methodology of the generation for the PV TRYs has been improved. The results are very good and the TRYs generated for these applications are adeguate to characterize the climatic condition of the place over a long period and can be used for energetic and environmental studies.

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Lo scopo della presente tesi di dottorato è di illustrare il lavoro svolto nella progettazione del circuito a metallo liquido del Test Blanket System (TBS) Helium Cooled Lithium Lead (HCLL), uno dei sistemi fondamentali del reattore sperimentale ITER che dovrà dimostrare la fattibilità di produrre industrialmente energia elettrica da processi di fusione nucleare. Il blanket HCLL costituisce una delle sei configurazioni che verranno testate in ITER, sulla base degli esperimenti condotti nei 10 dieci anni di vita del reattore verrà selezionata la configurazione che determinerà la costituzione del primo reattore dimostrativo per la produzione di un surplus di energia elettrica venti volte superiore all’energia consumata, DEMO. Il circuito ausiliario del blanket HCLL è finalizzato, in DEMO all’estrazione del trizio generato mediante il TES; ed in ITER alla dimostrazione della fattibilità di estrarre il trizio generato e di poter gestire il ciclo del trizio. Lo sviluppo dei componenti, svolto in questa tesi, è accentrato su tale dispositivo, il TES. In tale ambito si inseriscono le attività che sono descritte nei capitoli della seguente tesi di dottorato: selezione e progettazione preliminare del sistema di estrazione del trizio dalla lega eutettica Pb15.7Li del circuito a metallo liquido del TBM HCLL; la progettazione, realizzazione e qualifica dei sensori a permeazione per la misura della concentrazione di trizio nella lega eutettica Pb15.7Li; la qualificazione sperimentale all’interno dell’impianto TRIEX (TRItium EXtarction) della tecnologia selezionata per l’estrazione del trizio dalla lega; la progettazione della diagnostica di misura e controllo del circuito ausiliario del TBM HCLL.

The assessment of the RAMS (Reliability, Availability, Maintainability and Safety) performances of system generally includes the evaluations of the “Importance” of its components and/or of the basic parameters of the model through the use of the Importance Measures. The analytical equations proposed in this study allow the estimation of the first order Differential Importance Measure on the basis of the Birnbaum measures of components, under the hypothesis of uniform percentage changes of parameters. The aging phenomena are introduced into the model by assuming exponential-linear or Weibull distributions for the failure probabilities. An algorithm based on a combination of MonteCarlo simulation and Cellular Automata is applied in order to evaluate the performance of a networked system, made up of source nodes, user nodes and directed edges subjected to failure and repair. Importance Sampling techniques are used for the estimation of the first and total order Differential Importance Measures through only one simulation of the system “operational life”. All the output variables are computed contemporaneously on the basis of the same sequence of the involved components, event types (failure or repair) and transition times. The failure/repair probabilities are forced to be the same for all components; the transition times are sampled from the unbiased probability distributions or it can be also forced, for instance, by assuring the occurrence of at least a failure within the system operational life. The algorithm allows considering different types of maintenance actions: corrective maintenance that can be performed either immediately upon the component failure or upon finding that the component has failed for hidden failures that are not detected until an inspection; and preventive maintenance, that can be performed upon a fixed interval. It is possible to use a restoration factor to determine the age of the component after a repair or any other maintenance action.

This thesis deals with the study of optimal control problems for the incompressible Magnetohydrodynamics (MHD) equations. Particular attention to these problems arises from several applications in science and engineering, such as fission nuclear reactors with liquid metal coolant and aluminum casting in metallurgy. In such applications it is of great interest to achieve the control on the fluid state variables through the action of the magnetic Lorentz force. In this thesis we investigate a class of boundary optimal control problems, in which the flow is controlled through the boundary conditions of the magnetic field. Due to their complexity, these problems present various challenges in the definition of an adequate solution approach, both from a theoretical and from a computational point of view. In this thesis we propose a new boundary control approach, based on lifting functions of the boundary conditions, which yields both theoretical and numerical advantages. With the introduction of lifting functions, boundary control problems can be formulated as extended distributed problems. We consider a systematic mathematical formulation of these problems in terms of the minimization of a cost functional constrained by the MHD equations. The existence of a solution to the flow equations and to the optimal control problem are shown. The Lagrange multiplier technique is used to derive an optimality system from which candidate solutions for the control problem can be obtained. In order to achieve the numerical solution of this system, a finite element approximation is considered for the discretization together with an appropriate gradient-type algorithm. A finite element object-oriented library has been developed to obtain a parallel and multigrid computational implementation of the optimality system based on a multiphysics approach. Numerical results of two- and three-dimensional computations show that a possible minimum for the control problem can be computed in a robust and accurate manner.

In the present work, a multi physics simulation of an innovative safety system for light water nuclear reactor is performed, with the aim to increase the reliability of its main decay heat removal system. The system studied, denoted by the acronym PERSEO (in Pool Energy Removal System for Emergency Operation) is able to remove the decay power from the primary side of the light water nuclear reactor through a heat suppression pool. The experimental facility, located at SIET laboratories (PIACENZA), is an evolution of the Thermal Valve concept where the triggering valve is installed liquid side, on a line connecting two pools at the bottom. During the normal operation, the valve is closed, while in emergency conditions it opens, the heat exchanger is flooded with consequent heat transfer from the primary side to the pool side. In order to verify the correct system behavior during long term accidental transient, two main experimental PERSEO tests are analyzed. For this purpose, a coupling between the mono dimensional system code CATHARE, which reproduces the system scale behavior, with a three-dimensional CFD code NEPTUNE CFD, allowing a full investigation of the pools and the injector, is implemented. The coupling between the two codes is realized through the boundary conditions. In a first analysis, the facility is simulated by the system code CATHARE V2.5 to validate the results with the experimental data. The comparison of the numerical results obtained shows a different void distribution during the boiling conditions inside the heat suppression pool for the two cases of single nodalization and three volume nodalization scheme of the pool. Finaly, to improve the investigation capability of the void distribution inside the pool and the temperature stratification phenomena below the injector, a two and three dimensional CFD models with a simplified geometry of the system are adopted.

Calcolo della superficie curvilinea di scorrimento di un getto di litio in maniera che la pressione lungo il getto vari in maniera lineare. Formulazione di un codice di calcolo per la determinazione delle diverse possibili superfici. Studio termofluidodinamico del getto con codici CFD. Accoppiamento tra codici di sistema e codici CFD. Valutazioni delle condizioni di Incipient Boiling per il litio.