Burnup simulations of different fuel grades using the MCNPX Monte Carlo code
نویسندگان
چکیده
منابع مشابه
A Monte Carlo Burnup Code Linking Mcnp and Rebus*
The REBUS-3 burnup code, used in the ANL RERTR Program, is a very general code that uses diffusion theory (DIF3D) to obtain the fluxes required for reactor burnup analyses. Diffusion theory works well for most reactors. However, to include the effects of exact geometry and strong absorbers that are difficult to model using diffusion theory, a Monte Carlo method is required. MCNP, “a general-pur...
متن کاملMass Attenuation Coefficients of Human Body Organs using MCNPX Monte Carlo Code
Introduction: Investigation of radiation interaction with living organs has always been a thrust area in medical and radiation physics. The investigated results are being used in medical physics for developing improved and sensitive techniques and minimizing radiation exposure. In this study, mass attenuation coefficients of different human organs and biological materials such as adipose, blood...
متن کاملAssessment of secondary particles in breast proton therapy by Monte Carlo simulation code using MCNPX
Background: The present study aimed to investigate the equivalent dose in vital organs, including heart and lung, due to secondary particles produced during breast proton therapy. Materials and Methods: The numerical ORNL female-phantom was improved and simulated using the Monte Carlo MCNPX code. The depth-dose profile of proton beams with different energies was simulated. The proper energy ran...
متن کاملInvestigation of penetration depth of 63Ni beta spectrum in silicon by Monte Carlo method and using MCNPX code
In this study, the energy spectrum of beta-nickel 63 is considered as the total energy spectrum, average energy of the spectrum, and maximum spectral energy for analyzing the penetration depth of silicon. Monte Carlo calculations were carried out using a MCNPX code in a given geometry; in the following, Stopping-Power for electrons with different energies in silicon was calculated using the EST...
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 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: 2014
ISSN: 1451-3994,1452-8185
DOI: 10.2298/ntrp1404259a