نتایج جستجو برای: MCNP4C Code
تعداد نتایج: 167954 فیلتر نتایج به سال:
A 3D industrial computed tomography (CT) manufactured based on a first generation CT systems, single-source – single-detector, was evaluated. Operation accuracy assessment of the manufactured system was achieved using simulation in comparison with experimental tests. Cs and Co were used as a gamma source. Simulations were achieved using MCNP4C code. Experimental tests of Cs were in good agreeme...
introduction: clinical application of encapsulated radioactive brachytherapy sources has a major role in cancer treatment. in the present research, the effects of different tissue densities on the dose distribution of a 103pd brachytherapy source in a spherical phantom of 50 cm radius have been studied. material and methods: as is well known, absorbed dose in tissue depends to its density, but ...
background: the purpose of this study was to investigate the application of the monte carlo technique to calculate and analysis of dosimetric parameters for electron beams used in radiotherapy. this technique is based on statistical method and has a powerful role in different radiotherapy aspects. materials and methods: the simulated medical linear accelerator was the varian clinac 2100c. the e...
background: the presence of a wedge filter in the beam trajectory can modify the beam quality and cause some changes in the dosimetry parameters which are usually difficult to be measured directly and accurately. material and methods: in this study the mcnp-4c monte carlo code was used to simulate the 9 mv photon beam generated by a linear accelerator. upon getting a good agreement between the ...
In this paper MCNP4C code has been used to simulate of the photonuclear interaction induced by 10MeV electron beam is an approach for generating the high intensity neutrons. Since the results are depended on the target material, the calculations are performed for the targets made of high-z elements of Pb, Ta and W in a simple geometry.
The weight window variance reduction method in the general-purpose Monte Carlo N-Particle radiation transport code MCNP has recently been rewritten. In particular, it is now possible to generate weight window importance functions on a superimposed mesh, eliminating the need to subdivide geometries for variance reduction purposes. Our assessment addresses the following questions: (1) Does the n...
This paper is aimed to investigate the design of an optimized neutron radiography system that utilizes the flux of a reactor. Moderation, collimation aspects are studied. A Monte Carlo code, MCNP4C, was utilized to achieve a maximum and more homogenous neutron flux in the collimator outlet next to the image plane, taking into account geometric characteristics. It was possible to obtain a normal...
In this paper we propound a nondestructive and noninvasive technique for measuring the thickness of water penetration in a homogeneous slab. The proposed device consists of a 252 Cf spontaneous fission source and a set of 3 He detectors located on the same side of a concrete slab subject to water infiltration. The effectiveness of this technique has been investigated by Monte Carlo simulation...
It is well known that Intercrystal scattering (ICS) and the parallax effect are two major resolution limiting parameters in current PET detector designs with block detectors. More recently for the purpose of resolution recovery, investigators and manufacturers have attempted to accurately model these effects into the image reconstruction task. In this study we utilized the MCNP4C Monte Carlo co...
introduction: 90 sr/ 90 y source has been used for the intravascular brachytherapy to prevent coronary restenosis in the patients who have undergone angioplasty. the aim of this research is to determine the dose distribution of 90 sr/ 90 y source in a water phantom. materials and methods: in the present work, mcnp code has been applied to calculate the dose distri...
نمودار تعداد نتایج جستجو در هر سال
با کلیک روی نمودار نتایج را به سال انتشار فیلتر کنید