高级搜索

MCNP Dose Calculations in a CT Phantom for Therapeutic External Photon Beam

,  ,  ,  , 

downloadPDF

上一篇

下一篇

2011: MCNP Dose Calculations in a CT Phantom for Therapeutic External Photon Beam, 原子核物理评论, 28(2): 236-240.
引用本文: 2011: MCNP Dose Calculations in a CT Phantom for Therapeutic External Photon Beam, 原子核物理评论, 28(2): 236-240.
shu
Lamyae El Gonnouni, Tarek El Bardouni, Mariam Zoubair, Mohamed Idaornar, Abderrahmane Senhoo. 2011: MCNP Dose Calculations in a CT Phantom for Therapeutic External Photon Beam, Nuclear Physics Review, 28(2): 236-240.
Citation: Lamyae El Gonnouni, Tarek El Bardouni, Mariam Zoubair, Mohamed Idaornar, Abderrahmane Senhoo. 2011: MCNP Dose Calculations in a CT Phantom for Therapeutic External Photon Beam, Nuclear Physics Review, 28(2): 236-240.
shu

MCNP Dose Calculations in a CT Phantom for Therapeutic External Photon Beam

  • University Abdelmalek Essaadi , Faculty of Sciences, ERSN-LMR , Department of Physics, Tetuan, Morocco

  • University Abdelmalek Essaadi, Faculty of Sciences, BCM, Department of Biology, Tetuan, Morocco

  • National Institute of Oncology, NIO, Rabat, Morocco

MCNP Dose Calculations in a CT Phantom for Therapeutic External Photon Beam

  • 摘要: In this paper, we have addressed the problem of the radiation transport with the Monte Carlo N-particle(MCNP) code. This is a general-purpose Monte Carlo tool designed to transport neutron, photon and electron in three dimensional geometries. To examine the performance of MCNP5 code in the field of external radiotherapy, we performed the modeling of an Electron Density phantom (EDP) irradiated by photons from 60Co source. The model was used to calculate the Percent Depth Dose (PDD) at different depths in an EDP. One field size for PDD has been examined. A 60Co photons source placed at 80 cm source to surface distance (SSD). The results of calculations were compared to TPS data obtained at National Institute of Oncology of Rabat.
    Abstract: In this paper, we have addressed the problem of the radiation transport with the Monte Carlo N-particle(MCNP) code. This is a general-purpose Monte Carlo tool designed to transport neutron, photon and electron in three dimensional geometries. To examine the performance of MCNP5 code in the field of external radiotherapy, we performed the modeling of an Electron Density phantom (EDP) irradiated by photons from 60Co source. The model was used to calculate the Percent Depth Dose (PDD) at different depths in an EDP. One field size for PDD has been examined. A 60Co photons source placed at 80 cm source to surface distance (SSD). The results of calculations were compared to TPS data obtained at National Institute of Oncology of Rabat.
  • 加载中
  • 加载中
计量
  • 文章访问数:  322
  • HTML全文浏览数:  23
  • PDF下载数:  0
  • 施引文献:  0
出版历程
  • 刊出日期:  2011-06-20

MCNP Dose Calculations in a CT Phantom for Therapeutic External Photon Beam

  • University Abdelmalek Essaadi , Faculty of Sciences, ERSN-LMR , Department of Physics, Tetuan, Morocco
  • University Abdelmalek Essaadi, Faculty of Sciences, BCM, Department of Biology, Tetuan, Morocco
  • National Institute of Oncology, NIO, Rabat, Morocco

摘要: In this paper, we have addressed the problem of the radiation transport with the Monte Carlo N-particle(MCNP) code. This is a general-purpose Monte Carlo tool designed to transport neutron, photon and electron in three dimensional geometries. To examine the performance of MCNP5 code in the field of external radiotherapy, we performed the modeling of an Electron Density phantom (EDP) irradiated by photons from 60Co source. The model was used to calculate the Percent Depth Dose (PDD) at different depths in an EDP. One field size for PDD has been examined. A 60Co photons source placed at 80 cm source to surface distance (SSD). The results of calculations were compared to TPS data obtained at National Institute of Oncology of Rabat.

English Abstract

    全文HTML

参考文献 (0)

目录

/

返回文章
返回