نتایج جستجو برای: mcnp (4c) code
تعداد نتایج: 171417 فیلتر نتایج به سال:
introduction bnct is an effective method to destroy brain tumoral cells while sparing the healthy tissues. the recommended flux for epithermal neutrons is 109 n/cm2s, which has the most effectiveness on deep-seated tumors. in this paper, it is indicated that using d-t neutron source and optimizing of beam shaping assembly (bsa) leads to treating brain tumors in a reasonable time where all iaea ...
The neutron energy spectra have been calculated in the fuel region, inner and outer irradiation sites of the zero power research reactor using the MCNP-4C code and the combination of the WIMS-D/4 transport code for generation of group constants and the three-dimensional CITATION diffusion code for core analysis calculations. The neutron energy spectrum has been divided into three regions and co...
Response functions of a 3×3 in. NaI detector, which is mainly used in PGNAA applications, have been calculated by using MCNP-4C code. Calculated results are compared with measured data by using standard γ-ray sources to check their accuracy. γ-rays from radioisotope sources were used in the range from 0.081 to 4.438 MeV for this determination. Through the precise modeling of the detector struct...
Response functions of a 3×3 in. NaI detector, which is mainly used in PGNAA applications, have been calculated by using MCNP-4C code. Calculated results are compared with measured data by using standard -ray sources to check their accuracy. -rays from radioisotope sources were used in the range from 0.081 to 4.438 MeV for this determination. Through the precise modeling of the detector structur...
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...
ABSTRACTBackground: Monte Carlo simulation has been used by many researchers to calculate organ and effective dose of patients arising from conventional X-ray examinations. In this study the radiation transport code, MCNP-4C, has been used to perform Monte Carlo simulations to estimate radiation dose delivered to different organs in conventional X-ray examinations.Material and Methods: In this...
In this study MCNP-4C code is used to simulate the least shielding requirements for a mammography room. In order to simulate the X-ray tube, a molybdenum target is irradiated by 28 keV electrons. Then, a molybdenum filter with a thickness of 30 micrometers was used to remove the low-energy parts of X-ray spectrum. Finally the dosimetry evaluations were conducted after designing the lead shield ...
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 great challenge in simulations in the area of radiotherapy is to character the source, since the equipment’s manufacturers don’t provide specifics information about this. This work presents an empiric method for characterization of the ray-X beams of 6,0 MV and 10 MV originating from a linear accelerator of the mark Varian model 2100C. The experimental values of the percentage of deep dose (P...
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