Boron Neutron Capture Therapy (BNCT) is an advanced radiotherapy technique that relies on the neutron capture reaction of boron to selectively deliver high-LET radiation to tumor cells, requiring accurate real-time monitoring of the dose distribution. For this purpose, this study focuses on the development and simulation of a Prompt Gamma SPECT (PG-SPECT) system, which enables the detection of the characteristic 478 keV gamma rays emitted during neutron capture events. The system under investigation consists of a BeNEdiCTE detector coupled with a pinhole collimator, whose performance was evaluated through detailed Monte Carlo simulations using the FLUKA code. Key performance parameters, including spatial resolution, Field of View (FOV), and Point Spread Function (PSF), were assessed to characterize the system. A synthetic dataset including different sample geometries was generated to assess the reconstruction capabilities of the system. Simulations at three different angular positions of the detection system were performed to analyze the Signal-to-Background ratio for various sample configurations. Planar projections obtained from the simulations were used to perform three-dimensional image reconstruction using iterative algorithms, particularly MLEM algorithm implemented in MATLAB and OSEM algorithm within the STIR (Software for Tomographic Image Reconstruction) framework, allowing flexible modeling of the imaging system geometry. All simulations were conducted using the geometry of the LENA facility, including the PG-SPECT system analyzed in this work. The results demonstrate the feasibility of the simulated PG-SPECT system for dose monitoring in BNCT, despite the challenging high-background environment typical of BNCT treatments, providing a basis for further research toward the development of an online dose monitoring system capable of improving treatment planning accuracy.
La Boron Neutron Capture Therapy (BNCT) è una tecnica avanzata di radioterapia che sfrutta la reazione di cattura neutronica del boro per il rilascio selettivo di radiazione ad alto LET nelle cellule tumorali, richiedendo un accurato monitoraggio in tempo reale della distribuzione di dose. A tale scopo, questo lavoro si concentra sullo sviluppo e sulla simulazione di un sistema Prompt Gamma SPECT (PG-SPECT), in grado di rilevare i fotoni gamma caratteristici da 478 keV emessi durante gli eventi di cattura neutronica. Il sistema oggetto di studio è costituito da un rivelatore BeNEdiCTE accoppiato a un collimatore pinhole, le cui prestazioni sono state valutate mediante dettagliate simulazioni Monte Carlo utilizzando il codice FLUKA. I principali parametri prestazionali, tra cui risoluzione spaziale, Field Of View (FOV) e la Point Spread Function (PSF), sono stati analizzati al fine di caratterizzare il sistema. È stato generato un dataset sintetico con diverse geometrie di campione per valutare le capacità di ricostruzione del sistema. Simulazioni a tre differenti posizioni angolari del sistema di rivelazione sono state eseguite per analizzare il rapporto Segnale-Rumore di fondo (Signal-to-Background) per diverse configurazioni del campione. Le proiezioni planari ottenute dalle simulazioni sono state utilizzate per la ricostruzione tridimensionale delle immagini mediante algoritmi iterativi, in particolare l'algoritmo MLEM, implementato in MATLAB e l’algoritmo OSEM, all’interno del framework STIR (Software for Tomographic Image Reconstruction), consentendo una modellazione flessibile della geometria del sistema di imaging. Tutte le simulazioni sono state condotte utilizzando la geometria dell’impianto LENA, includendo il sistema PG-SPECT analizzato in questo lavoro. I risultati dimostrano la fattibilità del monitoraggio di dose nella BNCT mediante il sistema PG-SPECT simulato, nonostante il complesso ambiente ad alto background tipico di tali trattamenti, fornendo una base per ulteriori studi finalizzati allo sviluppo di un sistema di monitoraggio online della dose in grado di migliorare l’accuratezza del piano terapeutico.
A Pinhole SPECT collimator for BNCT: a Monte Carlo study
Cerone, Federica
2025/2026
Abstract
Boron Neutron Capture Therapy (BNCT) is an advanced radiotherapy technique that relies on the neutron capture reaction of boron to selectively deliver high-LET radiation to tumor cells, requiring accurate real-time monitoring of the dose distribution. For this purpose, this study focuses on the development and simulation of a Prompt Gamma SPECT (PG-SPECT) system, which enables the detection of the characteristic 478 keV gamma rays emitted during neutron capture events. The system under investigation consists of a BeNEdiCTE detector coupled with a pinhole collimator, whose performance was evaluated through detailed Monte Carlo simulations using the FLUKA code. Key performance parameters, including spatial resolution, Field of View (FOV), and Point Spread Function (PSF), were assessed to characterize the system. A synthetic dataset including different sample geometries was generated to assess the reconstruction capabilities of the system. Simulations at three different angular positions of the detection system were performed to analyze the Signal-to-Background ratio for various sample configurations. Planar projections obtained from the simulations were used to perform three-dimensional image reconstruction using iterative algorithms, particularly MLEM algorithm implemented in MATLAB and OSEM algorithm within the STIR (Software for Tomographic Image Reconstruction) framework, allowing flexible modeling of the imaging system geometry. All simulations were conducted using the geometry of the LENA facility, including the PG-SPECT system analyzed in this work. The results demonstrate the feasibility of the simulated PG-SPECT system for dose monitoring in BNCT, despite the challenging high-background environment typical of BNCT treatments, providing a basis for further research toward the development of an online dose monitoring system capable of improving treatment planning accuracy.| File | Dimensione | Formato | |
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2026_03_Cerone_Executive_Summary.pdf
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https://hdl.handle.net/10589/253210