نتایج جستجو برای: mcnp monte carlo code

تعداد نتایج: 236688  

Journal: :iranian journal of radiation research 0
a.a. mowlavi department of physics, tarbiat moallem university of sabzevar, p.o. box 397, sabzevar, iran a. binesh department of physics, payam nour university of fariman, fariman, iran h. moslehitabar department of physics, payam nour university of mashhad, mashhad, iran

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 30×30...

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Journal: :Revista espanola de medicina nuclear 2004
M Rodríguez Gual F F Lima R Sospedra Alfonso J González González C Calderón Marín

Interface software was developed to generate the input file to run Monte Carlo MCNP-4B code from medical image in Interfile format version 3.3. The software was tested using a spherical phantom of tomography slides with known cumulated activity distribution in Interfile format generated with IMAGAMMA medical image processing system. The 3D dose calculation obtained with Monte Carlo MCNP-4B code...

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Journal: :journal of paramedical sciences 0
rouhollah adeli central iran research complex (yazd), nuclear science and technology research institute (nstri), iran. seyed pezhman shirmardi central iran research complex (yazd), nuclear science and technology research institute (nstri), iran. jamal amiri department of radiotherapy, faculty of paramedical sciences, kurdistan university of medical sciences, sanandaj, iran v.p. singh department of physics, karnataka university, dharwad 580003, india. m.e. medhat experimental nuclear physics departments, nuclear research centre, p.o.13759, cairo, egypt

monte carlo method is a very accurate method to optimize medical diagnostic radiology spectra and simulation of radiation transportation. using mcnp code, radiology and mammography attenuated x-rayspectraweresimulated.the ipem report number 78 was used as a reference to compare with the geant4 and mcnp simulations because of its popularity and wide availability. the results of geant4 in 40kev s...

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Journal: :journal of medical signals and sensors 0
daryoush shahbazi-gahrouei saba ayat

introduction: radioiodine therapy is an effective method for treating thyroid cancer carcinoma, but it has some affects on normal tissues, hence dosimetry of vital organs are important to weigh the risks and benefits of this method. the aim of this study is to measure the absorbed doses of important organs by mcnp (monte carlo n particle) simulation and comparing the results of different method...

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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 ...

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1999
N. A. Hanan A. P. Olson R. B. Pond J. E. Matos

The REBUS-3 burnup code, used in the ANL RERTR Program, is a very general code that uses diffusion theory (DIF3D) to obtain the fluxes required for reactor burnup analyses. Diffusion theory works well for most reactors. However, to include the effects of exact geometry and strong absorbers that are difficult to model using diffusion theory, a Monte Carlo method is required. MCNP, “a general-pur...

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Journal: International Journal of Radiation Research 2006
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×...

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Journal: :iranian journal of radiation research 0
a.a. mowlavi physics department, school of sciences, sabzevar tarbiat moallem university, sabzevar, iran f. cupardo servizio di fisica sanitaria, ospedali riuniti di trieste, trieste, italy m. severgnini servizio di fisica sanitaria, ospedali riuniti di trieste, trieste, italy

background: monte carlo and experimental relative dose determination in a water phantom, due to a high dose rate (hdr) 192ir source is presented for real energy spectrum and monochromatic at 356 kev. materials and methods: the dose distribution has been calculated around the 192ir located in the center of 30 cm ×30 cm ×30 cm water phantom using mcnp4c code by monte carlo method. relative dose v...

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Journal: International Journal of Radiation Research 2008
A.A. Mowlavi, F. Cupardo, M. Severgnini,

Background: Monte Carlo and experimental relative dose determination in a water phantom, due to a high dose rate (HDR) 192Ir source is presented for real energy spectrum and monochromatic at 356 keV. Materials and Methods: The dose distribution has been calculated around the 192Ir located in the center of 30 cm ×30 cm ×30 cm water phantom using MCNP4C code by Monte Carlo method. Relati...

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Journal: :iranian journal of radiation research 0
m. yazdani department of physics, tarbiat moallem university of sabzevar, sabzevar, iran a.a. mowlavi department of physics, tarbiat moallem university of sabzevar, sabzevar, iran

background: monte carlo determination of tg-43 brachytherapy dosimetry parameters and dose distribution calculation for 131cs source model cs-1 are presented in this study. materials and methods: the dose distribution was calculated around the 131cs model cs-1 located in the center of 30 cm ×30 cm ×30 cm water, and soft tissue phantoms cube using mcnp code by monte carlo method. the percentage ...

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