| JI Gang,GUO Yong,LUO Yisheng.Calculation of dose distribution for 252Cf fission neutron source in tissue equivalent phantoms using Monte Carlo method[J].Chinese Journal of Radiological Medicine and Protection,2001,21(4):244-246 |
| Calculation of dose distribution for 252Cf fission neutron source in tissue equivalent phantoms using Monte Carlo method |
| Received:April 30, 2001 |
| DOI： |
| KeyWords:252Cf fission neutron source Monte Carlo Dose distribution Tissue equivalent phantom |
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| Abstract:: |
| Objective To provide useful parameters for neutron radiotherapy,this paper presents results of a Monte Carlo simulation study investigating the dosimetric characteristics of linear 252Cf fission neutron sources. Methods A 252Cf fission source and tissue equivalents phantom were modeled.The dose of neutron and gamma radiations were calculated using Monte Carlo Code. Results The dose of neutron and gamma at several positions for 252Cf in the phantom made of equivalent materials to water,blood,muscle,skin,bone and lung were calculated. Conclusion The results by Monte Carlo methods were compared with the data by measurements and references.According to the calculation,the method using water phantom to simulate local tissues such as muscle,blood and skin is reasonable for the calculation and measurements of dose distribution for 252Cf. |
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