نتایج جستجو برای: iridium_192 monte carlo mcnp

تعداد نتایج: 72882  

2007
PW Chin JP Giddy DG Lewis DW Walker

We present a computing framework for Monte Carlo simulation of radiation transport. In conformity with our belief that Monte Carlo studies should be anchored to physics but not to any particular code, we have enabled different Monte Carlo codes in this environment. The framework embraces the EGSnrc family, FLUKA, MCNP/MCNPX, GEANT4 and PENELOPE; dedicated and non-dedicated resources; shared and...

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 ...

A.A. Mowlavi, M. Yazdani,

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 ...

Journal: :iranian journal of radiation research 0
a.a. mowlavi physics department, school of sciences, tarbiat moallem university of sabzevar, p.o. box 397, sabzevar, iran.

abstractbackground: an electron beam generated x-ray spectrum consists of characteristic x-ray and continuous bermsstrahlung. the aim of this research is calculating and comparing x-ray spectra for different target filter of mammograms. materials and methods: monte carlo is a very powerful tool to simulate a series of different target-filter assembly in order to calculate the x-ray spectra. mcn...

A. Bozkurt, G. Kemikler, H. Acun,

Background: This study aims to calculate the air-kerma strength (SK), the dose rate constant (∧) and the dose rate profiles of a Gammamed 12i Ir-192 source by using the Monte Carlo technique and to compare the dose rate values with those calculated by the Abacus HDR treatment planning system (TPS). Materials and Methods: Air-kerma strength (in units of U; 1 U= μGy m2 h-1) and the dose ra...

Journal: :iranian journal of radiation research 0
h. nedaie department of medical physics, tehran university of medical sciences, tehran, iran m. shariary department of nuclear engineering, shahid beheshti university, tehran, iran h. gharaati department of medical physics, tehran university of medical sciences, tehran, iran m. allahverdi department of medical physics, tehran university of medical sciences, tehran, iran m.a. mosleh-shirazi joint department of physics, royal marsden hospital and institute of cancer research, surrey, uk

abstract background: accurate methods of radiation therapy dose calculation. there are different monte carlo codesfor simulation of photons, electrons and the coupled transport of electrons and photons. mcnpis a general purpose monte carlo code that can be used for electron, photon and coupledphoton-electron transport.monte carlo simulation of radiation transport is considered to be one of the ...

2006
B. Verboomen W. Haeck P. Baeten

The Monte Carlo calculation of the effective (i.e. adjoint weighted) neutron generation time Keff, especially for continuous energy simulations, is not straightforward nor standard in Monte Carlo codes. The use of the non-adjoint weighted neutron generation time K (standard in most Monte Carlo codes) as an approximation of the effective one can lead to a serious bias. We show here that the diff...

Journal: :Progress in Nuclear Science and Technology 2014

2003
Alexander Glaser Christoph Pistner

Modern technical computing environments, such as Mathematica or Matlab, provide powerful tools and techniques for research reactor analysis combined with advanced graphical user interfaces. In addition, reactor calculations can now be efficiently supported by neutronics codes based on the Monte Carlo method due to the dramatic increase of computer performance in recent years. In particular for ...

2008
Martin Schläger

This paper describes the mathematical efficiency calibration of the whole-body counter at Forschungszentrum Jülich using Monte Carlo codes and mathematical anthropomorphic phantoms. As a prerequisite for the Monte Carlo simulations a precise model of the 4 high-purity germanium (HPGe) detectors had to be developed. Because the technical data provided by the manufacturer were not sufficient for ...

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