نتایج جستجو برای: mcnpx

تعداد نتایج: 735  

Journal: :Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment 2020

Journal: :Sustainability 2022

The main objective of the present work was to assess gamma radiation shielding competencies and transmission factors (TFs) for some tellurite glasses in form Bi2O3–TeO2–Na2O–TiO2–ZnO. MCNPX general-purpose Monte Carlo code (version 2.6.0) utilized determination TF values at various well-known radioisotope energies different glass thicknesses from 0.5 cm 3 cm. Moreover, important ray properties ...

Journal: :Journal of materials research and technology 2021

In this study, a promising relationship between antibacterial zone and radiation attenuation properties was investigated in Ag2O doped bioactive glasses with chemical composition of xAg2O–20Li2O–25TeO2-(55-x)B2O3 (where x = 0, 0.5, 1.0, 1.5, 2.0 mol%). For aim, wide-ranging characterization procedure performed on substituted glasses. The general-purpose Monte Carlo code MCNPX (v.2.7.0) used to ...

Dariush Sardari Mahdi Sadeghi, Niloofar Azadegan Seyed Pezhman Shirmardi,

Introduction: The proton beam produced in particle accelerators has an appropriate therapeutic potential. In this research, proton therapy of breast cancer is simulated using the MCNPX code in a MIRD phantom, also the contribution of scattered neutron dose during the proton therapy were calculated for the Heart, Lung and Liver.   Materials and Methods: For si...

Journal: :Nuclear Technology & Radiation Protection 2022

This study presents neutronic analyses of a small modular reactor utilizing transuranium and thorium. Two different fuel cases are considered in the as extracted from PWR-MOX spent (a form mixture minor actinide Pu isotopes) (Case A) 4.5 % enriched UO2 with ThO 2(the separate rods) B). The total power containing 69 assemblies is 450 MW thermal. In both cases, time-dependent critical burnup calc...

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