نتایج جستجو برای: mcnp simulation code

تعداد نتایج: 704198  

2011
D. Krstic D. Nikezic

Series of mathematical phantoms of human body, given by Oak Ridge National Laboratory (ORNL), was programmed as input files for MCNP-4B code. Detailed check of geometry of these phantoms performed by MCNP-4B, discovered some minor errors, that resulted in overlapping of some organs. Three types of errors were found and described here: (a) colon overlaps with pelvis bone; (b) facial skeleton pen...

Journal: :Nuclear Engineering and Technology 2022

The MCS code is a computer developed by the Ulsan National Institute of Science and Technology (UNIST) for simulation calculation nuclear reactor systems based on Monte Carlo method. currently used to solve two main types physics problems, namely, criticality problems radiation shielding problems. In this paper, capability validated simulating some selected SINBAD (Shielding Integral Benchmark ...

Journal: :MRS Advances 2023

Abstract The contents and distribution of radionuclides in activated metallic wastes are major concerns while designing a leaching model safety case. This study investigated 60 Co as typical activation product the lower tie plate (i.e., stainless steel endpiece BWR fuel assembly) irradiated for 35.0 GWd/tHM burnup, using imaging (IP) method. calculations coupled with Monte Carlo burnup neutron ...

Journal: :Applied sciences 2021

In this paper, we present a useful Monte Carlo (MC)-based methodology that can be utilized to calculate the absorbed dose and initial levels of complex DNA damage (such as double strand breaks-DSBs) in case an environmental ionizing radiation (IR) exposure incident (REI) i.e., nuclear accident. Our objective is assess doses by isolating only one component total released environment after REI wi...

Journal: :iranian journal of medical physics 0
somayeh gholami m.sc., nuclear engineering dept., shahid beheshti university, tehran, iran alireza kamali asl assistant professor, nuclear engineering dept., shahid beheshti university, tehran, iran seyed mahmood aghamiri assistant professor, nuclear engineering dept., shahid beheshti university, tehran, iran mahmood allahverdi assistant professor, medical physics dept., tehran university, tehran, iran

introduction: gamma knife is an instrument specially designed for treating brain disorders. in gamma knife, there are 201 narrow beams of cobalt-60 sources that intersect at an isocenter point to treat brain tumors. the tumor is placed at the isocenter and is treated by the emitted gamma rays. therefore, there is a high dose at this point and a low dose is delivered to the normal tissue surroun...

Alireza Kamali Asl, Mahmood Allahverdi Seyed Mahmood Aghamiri Somayeh Gholami,

Introduction: Gamma Knife is an instrument specially designed for treating brain disorders. In Gamma Knife, there are 201 narrow beams of cobalt-60 sources that intersect at an isocenter point to treat brain tumors. The tumor is placed at the isocenter and is treated by the emitted gamma rays. Therefore, there is a high dose at this point and a low dose is delivered to the normal tissue surroun...

Journal: :iranian journal of radiation research 0
d. rezaei ochbelagh department of physics, university of mohageg ardebily, ardebil, iran h. miri hakimabad department of physics, faculty of sciences, ferdowsi university of mashhad, mashhad, iran r. izadi najafabadi department of physics, faculty of sciences, ferdowsi university of mashhad, mashhad, iran

background: several landmine detection methods, based on nuclear techniques, have been suggested during the recent years. neutron energy moderation, neutron-induced gamma emission, neutron and gamma attenuation, and fast neutron backscattering are nuclear-based methods used for landmine detection. the aim of this study is to use backscattered neutron for landmine detection. materials and method...

Journal: :iranian journal of radiation research 0
m. yazdani department of physics, tarbiat moallem university of sabzevar, sabzevar, iran a.a. mowlavi department of physics, tarbiat moallem university of sabzevar, sabzevar, iran

background: monte carlo determination of tg-43 brachytherapy dosimetry parameters and dose distribution calculation for 131cs source model cs-1 are presented in this study. materials and methods: the dose distribution was calculated around the 131cs model cs-1 located in the center of 30 cm ×30 cm ×30 cm water, and soft tissue phantoms cube using mcnp code by monte carlo method. the percentage ...

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Neutron dose-equivalent buildup factors were calculated for point isotropic neutron sources irradiating infinite slablike shields of lead, iron and water using the MCNP code. The factors are presented for some source neutron energies in the range from 0.025 eV to 14 MeV, and for shield thicknesses from 0.5 to 10 mfp. Since the MCNP code considers all kinds of neutron interactions with matter, a...

2012
C. M. Salgado R. Schirru

The Monte Carlo method was used to calculate the photon detection efficiency and energy resolution curves for a 1.500 100 NaI(Tl) scintillator detector (crystal þ housing þ photomultiplier tube material equivalent) exposed to gamma rays in the energy range from 20 keV to 662 keV. This work aims to design a precise computational model, based in Monte Carlo simulation, which can be used in practi...

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