Photoneutron dose and flux determination of a typical LINAC by MCNP simulation  

作　　者：Aydin Ghalehasadi Eren Sahiner Saleh Ashrafi Sasan Geranmayeh Hadi kasani Niyazi Meriç 

机构地区：[1]University of Tabriz,Tabriz,Iran [2]Institute of Nuclear Sciences,Ankara University,06100 Be¸sevler,Ankara,Turkey

出　　处：《Radiation Detection Technology and Methods》2021年第4期627-632,共6页辐射探测技术与方法（英文）

摘　　要：Purpose High-energy electron linear accelerators(LINACs)have a wide use in radiotherapy.The photoneutron production in medical linear accelerators,when operating at energies greater than 10 MeV,is an important subject to consider in patient’s treatment procedures.In this work,we simulate a typical LINAC to calculate photoneutron dose and flux in radiotherapy room.Methods The latest version of MCNPX Monte Carlo code along with MCNP visual editor has been used to simulate the LINAC and its components.Photoneutron production has been successfully simulated by selecting appropriate physics card and parameters.Dose and flux of produced photoneutrons have been calculated by using mesh tally function.Results Production of photoneutrons in LINAC head and its components have been successfully simulated by using MCNPX code.MCNP visual editor has been used to track the particles.Photoneutron dose and flux have been calculated using mesh tally function,with good results of statistical tests.Conclusion The photoneutron production has been successfully simulated and benchmarked.The proposed simulation code is able to calculate photoneutron dose and flux.According to photoneutron production cross sections,the appropriate parameters have been selected to reduce the run-time of simulation code.

关 键 词：LINAC PHOTONEUTRON DOSE FLUX MCNPX code 

分 类 号：TL5[核科学技术—核技术及应用]