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Application And Comparison Of GATE/MCNPX In The Determination Of Dose Conversion Coefficient In Human External Irradiation

Posted on:2019-11-04Degree:MasterType:Thesis
Country:ChinaCandidate:T T CuiFull Text:PDF
GTID:2371330548472989Subject:Biomedical engineering
Abstract/Summary:PDF Full Text Request
External radiation is the most common radiation exposure of human.The Monte Carlo method is used to simulate the dose conversion coefficient and it is a research hotspot in the field of radiation protection theory and application in the world.With the development of computer and scientific technology,new and powerful Monte Carlo simulation software has appeared.Applying this simulation software to radiation protection and comparing it with the other Monte Carlo software of simulation results,which not only provides a new path and method for calculating the dose of human exposure,but also the obtained data is more representative than the data obtained by a single Monte Carlo software.It is a great significance to accurately assess the dose received of the human body in the radiation field and promote the integration and application of the new Monte Carlo simulation software.In this paper,the common human body model of KTMAN-2(Korean typical MAN-2)in the mcnpx input file is converted to common image format(such as CT,etc)and special data format(such GATE)by in-code algorithm.This bi-directional conversion realize the real-time interactive visualization of complex voxel model.Based on the purposes of verification,comparison,and application,under the same voxel model conditions,GATE and MCNPX were used to simulate the dose conversion coefficients of human organs with different photon and neutron energies in the six standard irradiation geometries,then compared the two calculated results.And compare the organ absorbed dose conversion coefficients with the recommended values of ICRP 74,ICRP 116 publication.The main results are as follows:(1)Calculate the absorbed doses of human organs in different photon and neutron energies under AP,PA,LLAT,RLAT,ROT,and ISO standard irradiation geometries in the GATE and MCNPX programs and compare the differences of results differences.In addition,systematically analyzed the difference between the calculated results of this paper and the reference doses of ICRP 74 and ICRP 116 publications.(2)The data of the human voxel model in MCNP/MCNPX is converted into CT format by in-code Matlab code.This method solves the problem of in the absence of human voxel model raw image data that could not be used by other Monte Carlos to further validation due to the differences in the input file,providing a new method for ensuring the accuracy of the dose calculation.(3)This paper also studied and compared the calculation accuracy of GATE Livermore,Penelope and Standard package in the external irradiation of photons.The results show that Livermore package has better stability and it is slightly more accurate than Standard and Penelope packages.This result provides a reference for the selection of the electromagnetic model package in GATE's similar research work.
Keywords/Search Tags:Human voxel phantom, Dose conversion coefficient, GATE/MCNPX, KTMAN-2
PDF Full Text Request
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