Design of 6Mev linear accelerator based pulsed thermal neutron source: FLUKA simulation and experiment

Optimization of a photoneutron source based on 10MeV electron beam using Geant4 Monte Carlo code

“…The usage of Monte Carlo technique requires the reproduction of the photonuclear and electronuclear reactions in great detail, as they are the only reactions converting electromagnetic energy of electrons, positrons, and photons to hadronic energy of mesons, nuclear fragments, and soft neutrons. Reliable Monte Carlo codes such as MCNP [3] and Fluka [4] have been widely used to perform simulation studies to model and optimize the photoneutron target that derives from accelerated electrons [5][6][7][8][9]. In certain references, the obtained results were in good agreement with the experimental tests [6,7].…”

“…It is worth to mention that Fluka code has been validated against experimental results as reported in the literature [7,20]. In Ref.…”

An investigation of the neutron flux in bone-fluorine phantoms comparing accelerator based in vivo neutron activation analysis and FLUKA simulation data

“…The experiment and the Monte Carlo simulated neutron flux results were found to be consistent. This is not surprising: FLUKA has been used in several studies and is validated by various experiments [33][34][35][36]. We matched the FLUKA data to experimental results obtained via fairly standard methodology of measurements of neutron fluxes using Mn activation foils as has been performed in multiple studies [23,21,22,43,42,41], and often around accelerators which have been used as a neutron source for therapy purposes [28,13,8,39,27].…”

“…FLUKA has been previously shown to be an extremely useful tool in the field of radiation physics [33][34][35][36]. It is a multipurpose transport Monte Carlo code for calculations of particle transport and interactions with matter, covering an extended range of applications such as proton and electron accelerators.…”

Design of photon converter and photoneutron target for High power electron accelerator based BNCT

“…Energy and intensity of neutron beam should be chosen to maximize thermal neutron density in the proximity of the tumor area (Bisceglie et al, 2002), so the appropriate therapeutic neutron energy is in the 0.4 eV-10 keV range at the beam port. There are several neutron sources for BNCT (Patil et al, 2012;Burian et al, 2006;Martin et al, 2000;Durisi et al, 2007). Linear electron accelerators are rather cheap, compact, easy handling, low cost with less complexity.…”