نتایج جستجو برای: mcnp design

تعداد نتایج: 960935  

Journal: :iranian journal of medical physics 0
vahid moslemi m.sc. in medical radiation engineering, medical radiation dept., faculty of mechanical engineering, shiraz university, shiraz, iran ahmad esmaili-torshabi m.sc. in medical radiation engineering, medical radiation dept., faculty of mechanical engineering, shiraz university, shiraz, iran mohammad amin mosleh-shirazi assistant professor, radiotherapy and oncology dept., center of research in medical physics and engineering, shiraz university of medical sciences, shiraz, iran reza faghihi assistant professor, nuclear engineering, center of radiation research, shiraz university, shiraz, iran ahmad mosalaei professor, radiotherapy and oncology dept., shiraz university of medical sciences, shiraz, iran simin mehdizadeh m.sc., nuclear engineering, center of radiation research, shiraz university, shiraz, iran

introduction: in brachytherapy, radioactive sources are placed close to the tumor, therefore, small changes in their positions can cause large changes in the dose distribution. this emphasizes the need for computerized treatment planning. the usual method for treatment planning of cervix brachytherapy uses conventional radiographs in the manchester system. nowadays, because of their advantages ...

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...

2007
D. V. Fedorchenko

Design and maintenance of nuclear cycle facilities mandatory imply implementation of efficient radiation protection. Radiation environment assessment and shielding optimization require a considerable amount of numerical calculations. Nowadays mathematical modelling methods and corresponding software are widely used for such kind of problems. All the software used for radiation fields modelling ...

Journal: :Baghdad Science Journal 2022

In this paper, the Monte Carlo N-Particle extended computer code (MCNP) were used to design a model of European Sodium-cooled Fast Reactor. The multiplication factor, conversion delayed neutrons fraction, doppler constant, control rod worth, sodium void masses for major heavy nuclei, radial and axial power distribution at high burnup are studied. results show that reactor breeds fissile isotope...

2000
J. Stanley A. M. Oros-Peusquens J. Prisciandaro

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...

2008
Jacquelyn C. Yanch Sheena Hembrador

The biological effects of acute, high doses of radiation are well understood. However, the effects of chronic, low doses are not as clear. Mice irradiation experiments to study the correlation of biological effects with chronic low dose rates are underway in order to make conclusions about the effects of low doses. Yet, in order to do so, the level of dose provided to the animals must be determ...

2010
Zaixin Li Kaiming Feng Guoshu Zhang Guoyao Zheng Tao Yuan

The Neutron induced activity and decay heat are very important for the nuclear design of fusion reactor. In this paper, activation analysis of DEMO reactor with helium-cooled solid blanket (HCSB-DEMO) was performed. Ceramics Li4SiO4 and Beryllium options were considered as tritium breeding material and neutron multiplier, respectively. Chinese low-activation ferritic steel (CLF-1) developed in ...

2009
M. E. Sawan

MCNP calculations for a calculational benchmark representative of an early ITER design were carried out to investigate the impact of ENDF/B-VII.0 release on FENDL-2.1. The results presented in this work clearly show that the previously observed differences in nuclear heating and radiation damage are removed when the correctly processed ENDF/BVII.0 data are used. Differences in all nuclear param...

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