A Monte Carlo-aided design of a modular 241Am-Be neutron irradiator
نویسندگان
چکیده
منابع مشابه
A Monte Carlo study of SPECT in boron neutron capture therapy for a heterogeneous human phantom
Background: Boron neutron capture therapy (BNCT) is a binary radiotherapy combining biochemical targeting with neutron irradiation. However, monitoring the boron distribution is a fundamental problem in BNCT. Prompt gamma rays emitted by boron capture reaction can be used to address the issue. Materials and Methods: The general-purpose Monte Carlo toolkits Geant4 and MCNP were used for the simu...
متن کاملDesign and Simulation of Photoneutron Source by MCNPX Monte Carlo Code for Boron Neutron Capture Therapy
Introduction Electron linear accelerator (LINAC) can be used for neutron production in Boron Neutron Capture Therapy (BNCT). BNCT is an external radiotherapeutic method for the treatment of some cancers. In this study, Varian 2300 C/D LINAC was simulated as an electron accelerator-based photoneutron source to provide a suitable neutron flux for BNCT. Materials and Methods Photoneutron sources w...
متن کاملExperimental and Monte Carlo studies on the response of CR-39 detectors to Am-Be neutron spectrum
Background: The Poly-Allyl Diglycol Carbonate (PADC) detector is of particular interest for development of a fast neutron dosimeter. Fast neutrons interact with the constituents of the CR-39 detector and produce H, C and O recoils, as well as (n, α) reaction. These neutron- induced charged particles contribute towards the response of CR-39 detectors. Material and Methods: Electrochemical...
متن کاملdesign and simulation of photoneutron source by mcnpx monte carlo code for boron neutron capture therapy
introduction electron linear accelerator (linac) can be used for neutron production in boron neutron capture therapy (bnct). bnct is an external radiotherapeutic method for the treatment of some cancers. in this study, varian 2300 c/d linac was simulated as an electron accelerator-based photoneutron source to provide a suitable neutron flux for bnct. materials and methods photoneutron sources w...
متن کاملMonte Carlo Calculations Using MCNP4B for an Optimal Shielding Design of a 14-MeV Neutron Source
The shielding for 14-MeV neutrons from a D-T generator at SLAC needs to be optimized in terms of shield thickness and cost. Shielding calculations were made using the MCNP4B Monte Carlo code and the ENDF/B-VI cross section set. A few materials were studied: iron, borated polyethylene, three types of normal and heavy concrete, and mixtures of iron and borated polyethylene. The effects of shieldi...
متن کاملذخیره در منابع من
با ذخیره ی این منبع در منابع من، دسترسی به آن را برای استفاده های بعدی آسان تر کنید
ژورنال
عنوان ژورنال: Nuclear Technology and Radiation Protection
سال: 2013
ISSN: 1451-3994
DOI: 10.2298/ntrp1303265b