نتایج جستجو برای: mcnp code

تعداد نتایج: 168334  

Journal: :Indonesian Journal of Physics and Nuclear Applications 2016

Journal: :HNPS Advances in Nuclear Physics 2023

The true coincidence effect is studied in two High Purity Germanium (HPGe) detectors for a variety of isotopes, source geometries and to detector configurations, via computational tools based on Monte–Carlo simulations. Τhe upgraded patch MCNP code MCNP–CP the 2018 version PENELOPE, which take into account decay scheme each cascade emitter, are used calculate Full Energy Peak Efficiency (FEPE) ...

ژورنال: سنجش و ایمنی پرتو 2020

Radiation protection and the selection of suitable materials to reduce radiation effects is one of the important branches of medical science and radiation. In this paper, the mass attenuation coefficients, half value layer thicknesses and thicknesses of 0/5 mm lead of polyvinyl chloride (PVC) composites containing Nano and micro-particles of copper oxide are calculated using experimental method...

2005
Jaakko Leppänen

This paper presents a new assembly-level Monte Carlo neutron transport code, specifically intended for diffusion code group-constant generation and other reactor physics calculations. The code is being developed at the Technical Research Centre of Finland (VTT), under the working title “Probabilistic Scattering Game”, or PSG. The PSG code uses a method known as Woodcock tracking to simulate neu...

2017
A. Mostaar M. Allahverdi M. Shahriari

Background: In treating patients with radiation, the degree of accuracy for the delivery of tumor dose is recommended to be within ± 5% by ICRU in report 24. The experimental studies have shown that the presence of low-density inhomogeneity in areas such as the lung can lead to a greater than 30% change in the water dose data. Therefore, inhomogeneity corrections should be used in treatment pla...

آقامیری , سید محمودرضا , جابری, رامین , مجرد کاهانی, محمدمهدی , هاشمی, سمانه ,

Background and purpose: Concave eye applicators of Ru-106, a beta emitter source, have a lot of use in brachytherapy of intraocular tumors. This has led to the need of knowing the exact dose distribution caused by beta radiation to the tumor and its normal surrounding tissue. The purpose of this study was the 3D calculation of dose distribution for three Ru-106 plaques: CCA, CCB, and CGD in a h...

A. Binesh, A.A. Mowlavi, H. Moslehitabar,

Background: Palladium-103 (103Pd) is a brachytherapy source for cancer treatment. The Monte Carlo codes are usually applied for dose distribution and effect of shieldings. Monte Carlo calculation of dose distribution in water phantom due to a MED3633 103Pd source is presented in this work. Materials and Methods: The dose distribution around the 103Pd Model MED3633 located in the center of 30×...

Ghafourian, Haji-Shafeieha, Kakavand,

Background: Miniature neutron sources with high neutron flux have abundant applications in medicine, industry and researches. The most important general characteristic of miniature neutron sources is their diameter which is 3mm in average. In this research, we have surveyed and designed an Am-Be miniature neutron source fabrication. Materials and Methods: This investigation resulted in creation...

2007
Sara A. Pozzi Marek Flaska Andreas Enqvist

We describe the use of the MCNP-PoliMi code to simulate, on an event-by-event basis, the detection of neutrons by organic scintillators. This code keeps track of single neutron interactions, including the collision nucleus, the energy deposited, and the time distribution of collision events. We show that the total pulse-height response is given by the sum of many possible neutron histories, eac...

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