Calculation of the eigenfunctions of the two-group neutron diffusion equation and application to modal decomposition of BWR instabilities

In this thesis, numerical methods aiming at determining the eigenfunctions, their adjoint and the corresponding eigenvalues of the two-group neutron diffusion equations representing any heterogeneous system are investigated. First, the classical power iteration method is modified so that the calculation of modes higher than the fundamental mode is possible. Thereafter, the Explicitly-Restarted Arnoldi method, belonging to the class of Krylov subspace methods, is touched upon. Although the modified power iteration method is a computationally-expensive algorithm, its main advantage is its robustness, i.e. the method always converges to the desired eigenfunctions without any need from the user to set up any parameter in the algorithm. On the other hand, the Arnoldi method, which requires some parameters to be defined by the user, is a very efficient method for calculating eigenfunctions of large sparse system of equations with a minimum computational effort. These methods are thereafter used for off-line analysis of the stability of Boiling Water Reactors. Since several oscillation modes are usually excited (global and regional oscillations) when unstable conditions are encountered, the characterization of the stability of the reactor using for instance the Decay Ratio as a stability indicator might be difficult if the contribution from each of the modes are not separated from each other. Such a modal decomposition is applied to a stability test performed at the Swedish Ringhals-1 unit in September 2002, after the use of the Arnoldi method for pre-calculating the different eigenmodes of the neutron flux throughout the reactor. The modal decomposition clearly demonstrates the excitation of both the global and regional oscillations. Furthermore, such oscillations are found to be intermittent with a time-varying phase shift between the first and second azimuthal modes.

Modelling and analysis of internally BFRP reinforced beams at elevated temperatures

The aim of the work is to conduct a finite element model analysis on a small – size concrete beam and on a full size concrete beam internally reinforced with BFRP exposed at elevated temperatures. Experimental tests performed at Kingston University have been used to compare the results from the numerical analysis for the small – size concrete beam. Once the behavior of the small – size beam at room temperature is investigated and switching to the heating phase reinforced beams are tested at 100°C, 200°C and 300°C in loaded condition. The aim of the finite element analysis is to reflect the three – point bending test adopted into the oven during the exposure of the beam at room temperature and at elevated temperatures. Performance and deformability of reinforced beams are straightly correlated to the material properties and a wide analysis on elastic modulus and coefficient of thermal expansion is given in this work. Develop a good correlation between the numerical model and the experimental test is the main objective of the analysis on the small – size concrete beam, for both modelling the aim is also to estimate which is the deterioration of the material properties due to the heating process and the influence of different parameters on the final result. The focus of the full – size modelling which involved the last part of this work is to evaluate the effect of elevated temperatures, the material deterioration and the deflection trend on a reinforced beam characterized by a different size. A comparison between the results from different modelling has been developed.

Monte Carlo simulation of the WENDI-2 neutron dosimeter

Il presente lavoro di tesi, sviluppato nell’arco di sei mesi presso l’Institut Supérieur Industriel de Bruxelles (ISIB) in collaborazione con Ion Beam Application Group (IBA, Louvain la Neuve), ha come principale soggetto lo studio della risposta del rem meter WENDI-2 commercializzato da Thermo Scientific. Lo studio si è basato principalmente sull’uso del codice Monte Carlo MCNPX 2.5.0, simulando la risposta del detector sia in caso di campi di radiazione neutronica monoenergetici sia in corrispondenza di spettri neutronici continui. La prima fase è stata dedicata alla modellizzazione MCNPX del rem counter, consentendo così la valutazione della sua funzione risposta. Questa è stata ricostruita interpolando 93 punti, ciascuno calcolato in corrispondenza di un singolo valore di energia di una sorgente puntiforme, compreso tra 1 meV e 5 GeV. In tal caso è stata rilevata un’ottima corrispondenza tra i risultati ottenuti e quelli riportati nella letteratura scientifica esistente. In una seconda fase, al fine di ottenere informazioni sulla risposta di WENDI II in corrispondenza di campi complessi di radiazione, simulazioni MCNPX sono state realizzate riproducendo un ambiente di lavoro esistente presso la sede IBA di Louvain la Neuve: la risposta del detector è stata valutata in corrispondenza di 9 diverse posizioni all’interno di un bunker contenente un ciclotrone PET (18 MeV H-), implicando la rilevazione di campi di radiazione neutronica continui ed estesi dalle energie termiche fino a 18 MeV. I risultati ottenuti sono stati infine comparati con i valori di dose ambiente equivalente calcolata nelle stesse condizioni di irraggiamento.

Neutron radiation resistance of photomultipliers for the LUCID detector in the ATLAS experiment at LHC

Durante il Long Shutdown 1 di LHC sono stati cambiati i fotomoltiplicatori del rivelatore di luminosità LUCID di ATLAS. I due modelli candidati per la sostituzione sono stati sottoposti a test di resistenza alla radiazione di gamma e neutroni. In questa tesi si riportano i risultati delle misure di dark current, risposta spettrale, guadagno relativo e assoluto, prima e dopo l’irraggiamento con neutroni. L’unica differenza di rilievo riguarda un aumento della dark current, gli altri parametri non presentano variazioni entro la precisione delle misure. Non ci sono differenze sostanziali tra i due modelli per quanto riguarda la resistenza alle radiazioni.

Radiotherapy with scanning carbon ion beams: biological dose analysis for partial treatment delivery

L’uso di particelle cariche pesanti in radioterapia prende il nome di adroterapia. L’adroterapia permette l’irraggiamento di un volume bersaglio minimizzando il danno ai tessuti sani circostanti rispetto alla radioterapia tradizionale a raggi X. Le proprietà radiobiologiche degli ioni carbonio rappresentano un problema per i modelli radiobiologici a causa della non linearità della loro efficacia biologica. In questa tesi presenteremo gli algoritmi che possono essere usati per calcolare la dose fisica e biologica per un piano di trattamento del CNAO (Centro Nazionale Adroterapia Oncologica). Un caso di particolare interesse è l’eventualità che un piano di trattamento venga interrotto prima del dovuto. A causa della non linearità della sopravvivenza cellulare al variare della quantità di dose ricevuta giornalmente, è necessario studiare gli effetti degli irraggiamenti parziali utilizzando algoritmi che tengano conto delle tante variabili che caratterizzano sia i fasci di ioni che i tessuti irraggiati. Nell'ambito di questa tesi, appositi algoritmi in MATLAB sono stati sviluppati e implementati per confrontare la dose biologica e fisica assorbita nei casi di trattamento parziale.

Pulse shape studies of neutral particles with a liquid scintillator

The hadrontherapy exploits beams of charged particles against deep cancers. These ions have a depth-dose profile in which there is a little release of energy at the beginning of their path, whereas there is a sharp maximum, the Bragg Peak, near its end path. However, if heavy ions are used, the fragmentation of the projectile can happen and the fragments can release some dose outside the treatment volume beyond the Bragg peak. The fragmentation process takes place also when the Galactic Cosmic Rays at high energy hit the spaceship during space missions. In both cases some neutrons can be produced and if they interact with the absorbing materials nuclei some secondary particles are generated which can release energy. For this reason, studies about the cross section measurements of the fragments generated during the collisions of heavy ions against the tissues nuclei are very important. In this context, the FragmentatiOn Of Target (FOOT) experiment was born, and aims at measuring the differential and double differential fragmentation cross sections for different kinetic energies relevant to hadrontherapy and space radioprotection with high accuracy. Since during fragmentation processes also neutrons are produced, tests of a neutron detection system are ongoing. In particular, recently a neutron detector made up of a liquid organic scintillator, BC-501A with neutrons/gammas discrimination capability was studied, and it represents the core of this thesis. More in details, an analysis of the data collected at the GSI laboratory, in Darmstadt, Germany, is effectuated which consists in discriminating neutral and charged particles and then to separate neutrons from gammas. From this analysis, a preliminary energy-differential reaction cross-section for the production of neutrons in the 16O + (C_2H_4)_(n) and 16O + C reactions was estimated.

Debonding and crack propagation in cracked steel beams strengthened with CFRP and subjected to cyclic loads.

The reinforcement methods used to restore or increase the bearing capacity of metal structures are based on the application of steel plates to be bolted or welded to the original structure, which can cause problems to the integrity of the original structure. These difficulties can be overcome with the introduction of fiber-reinforced composite materials. FRPs are characterized by high strength to weight ratio, and they are very resistant to corrosion. In this dissertation a cracked steel I-beam reinforced with Carbon Fiber-Reinforced Polymer will be studied by performing a numerical evaluation of the structure with the commercial Finite Element Method software ABAQUS. The crack propagation will be computed using XFEM, while the debonding of the reinforcement layer will be found by considering a cohesive contact interface between the beam and the CFRP plate. The results will show the efficiency of the strengthening method in increasing the load carrying capacity of the cracked beam, and in reducing the crack opening of the initial notch.