نتایج جستجو برای: mcnp calculation

تعداد نتایج: 102713  

 ABSTRACTBackground: An electron beam generated X-ray spectrum consists of characteristic X-ray and continuous bermsstrahlung. The aim of this research is calculating and comparing X-ray spectra for different target filter of mammograms. Materials and Methods: Monte Carlo is a very powerful tool to simulate a series of different target-filter assembly in order to calculate the X-ray spectra. MC...

F. Taghdiri, M. Athari, M. Sadeghi, S.H. Hosseini,

Background: The formalism recommended by Task Group 60 (TG-60) of the American Association of Physicists in Medicine (AAPM) is applicable for β sources. Radioactive biocompatible and biodegradable 153Sm glass seed without encapsulation is a β- emitter with a short half life and delivers a high dose rate to the tumor in the millimeter range. In this work the dosimetry parameters of the ...

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 ...

2012
Craig M. Marianno Sunil S. Chirayath William S. Charlton Sunil P. Khatri Yassin A. Hassan Sunil S Chirayath Sunil Chirayath

Radiation Transport Simulation Studies Using MCNP for a Cow Phantom to Determine an Optimal Detector Configuration for a New Livestock Portal. (August 2012) Joe Justina, M.Sc., Mangalore University Co-Chairs of Advisory Committee: Dr. Craig M. Marianno Dr. Sunil S. Chirayath A large radiological accident will result in the contamination of surrounding people, animal, vegetation etc. In such a s...

Journal: :Health physics 2017
Michael W McNaughton Jessica M Gillis Elizabeth Ruedig Jeffrey J Whicker David P Fuehne

Standard plume models can underestimate the gamma-ray dose when most of the radioactive material is above the heads of the receptors. Typically, a model is used to calculate the air concentration at the height of the receptor, and the dose is calculated by multiplying the air concentration by a concentration-to-dose conversion factor. Models indicate that if the plume is emitted from a stack du...

Journal: :Physics in medicine and biology 2002
John J Demarco Robert E Wallace Kirsten Boedeker

Monte Carlo calculations are frequently used to analyse a variety of radiological science applications using low-energy (10-1000 keV) photon sources. This study seeks to create a low-energy benchmark for the MCNP Monte Carlo code by simulating the absolute dose rate in water and the air-kerma rate for monoenergetic point sources with energies between 10 keV and 1 MeV. The analysis compares four...

Journal: :iranian journal of science and technology (sciences) 2009
k. hadad

in this study, a general theoretical model to foresee and calculate the current-voltagecharacteristics in a plateau zone and the associated efficiency of the neutron detector (sensitivity) is presented. this study is to complete the previous studies in this field. the model also considers electric field distortion resulting from the charge collection effect. the characteristics curve is obtaine...

Seyed Farhad Masoudi, Somayeh Asadi, Zohreh Dehghannia Rostami

Introduction: In this paper, by complete definition of human eye containing the various parts and their materials, the difference between this model and a homogeneous water phantom are compared for two ophthalmic plaques using 125I and 103Pd. Material and methods: The simulation of the two phantoms were performed in the MCNP-4C code and by using the geometry of a three-dimensional eye, differen...

رنجبر, لیلا, شهابی, ایرج, شیرانی, احمد,

In this work, the Isfahan Miniature Neutron Source Reactor (MNSR) is first simulated using the WIMSD code, and its fuel burn-up after 7 years of operation ( when the reactor was revived by adding a 1.5 mm thick beryllium shim plate to the top of its core) and also after 14 years of operation (total operation time of the reactor) is calculated. The reactor is then simulated using the MCNP code,...

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