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

Radiation Detection Technology and Methods 2021年第4期5卷 627-632页

作者： Aydin Ghalehasadi Eren Sahiner Saleh Ashrafi Sasan Geranmayeh Hadi kasani Niyazi Meriç University of Tabriz TabrizIran Institute of Nuclear Sciences Ankara University06100 Be¸sevlerAnkaraTurkey

Purpose High-energy electron linear accelerators(LINACs)have a wide use in *** photoneutron production in medical linear accelerators,when operating at energies greater than 10 MeV,is an important subject to consider in patient’s treatment *** this work,we simulate a typical LINAC to calculate photoneutron dose and flux in radiotherapy *** The latest version of MCNPX Monte Carlo code along with MCNP visual editor has been used to simulate the LINAC and its *** production has been successfully simulated by selecting appropriate physics card and *** and flux of produced photoneutrons have been calculated by using mesh tally *** Production of photoneutrons in LINAC head and its components have been successfully simulated by using MCNPX *** visual editor has been used to track the *** dose and flux have been calculated using mesh tally function,with good results of statistical *** The photoneutron production has been successfully simulated and *** proposed simulation code is able to calculate photoneutron dose and *** 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

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Monte Carlo simulation for bremsstrahlung and photoneutron yields in high-energy x-ray radiography

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Chinese Physics B 2010年第6期19卷 213-220页

作者：许海波彭现科陈朝斌 Institute of Applied Physics and Computational Mathematics

This paper reports on the results of calculations using a Monte Carlo code （MCNP5） to study the properties of photons, electrons and photoneutrons obtained in the converted target and their transportations in x-ray radiography. A comparison between measurements and calculations for bremsstrahlung and photoneutrons is presented. The radiographic rule and the effect of the collimator on the image are studied with the experimental model. The results provide exact parameters for the optimal design of radiographic layout and shielding systems.

关键词： x-ray radiography bremsstrahlung photoneutron energy spectrum angular distribution

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Study on inherent neutron sources in MSR

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Nuclear Science and Techniques 2018年第4期29卷 146-154页

作者： Rui-Min Ji Cheng-Gang Yu Ming-Hai Li Rui Yan Yang Zou Gui-Min Liu Shanghai Institute of Applied Physics Chinese Academy of Sciences Jiading Campus Shanghai 201800 China University of Chinese Academy of Sciences Beijing 100049China

The molten salt reactor(MSR) has received much recent attention. The presence of beryllium and the mixing of actinides with light nuclei in the fuel salt result in a relatively strong neutron source that can affect the surveillance at subcritical and transient characteristics during operation. In this study, we predict the inherent neutron sources based on a MSR model. The calculation shows that in the fresh core, the inherent neutron sources are mainly from alpha-induced neutrons. After power operation, the inherent neutron sources become remarkably stronger due to photoneutrons. Although being an insignificant part in the total neutron population during operation, the inherent neutron sources can be used as the installed neutron source after shutdown. If the MSR has continuously operated at full power(2 MWt) for 10 days,then there would be no need for the installed source within80 days after shutdown. After operating constantly for500 days, the installed neutron source can be eliminated within 2 years after shutdown.

关键词： MSR Fuel salt Inherent neutron source photoneutron Alpha-induced neutron

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