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MCNP/MCNPX几何栅元划分方法对精确放疗剂量计算的影响研究

赵攀 陈义学 林辉 郑善良 吴宜灿

赵攀, 陈义学, 林辉, 郑善良, 吴宜灿. MCNP/MCNPX几何栅元划分方法对精确放疗剂量计算的影响研究[J]. 原子核物理评论, 2006, 23(2): 258-262. doi: 10.11804/NuclPhysRev.23.02.258
引用本文: 赵攀, 陈义学, 林辉, 郑善良, 吴宜灿. MCNP/MCNPX几何栅元划分方法对精确放疗剂量计算的影响研究[J]. 原子核物理评论, 2006, 23(2): 258-262. doi: 10.11804/NuclPhysRev.23.02.258
ZHAO Pan, CHEN Yi-xue, LIN Hui, ZHENG Shan-liang, WU Yi-can. Effect of Different Voxel-uniting Methods on the Dose Calculation of MCNP/MCNPX[J]. Nuclear Physics Review, 2006, 23(2): 258-262. doi: 10.11804/NuclPhysRev.23.02.258
Citation: ZHAO Pan, CHEN Yi-xue, LIN Hui, ZHENG Shan-liang, WU Yi-can. Effect of Different Voxel-uniting Methods on the Dose Calculation of MCNP/MCNPX[J]. Nuclear Physics Review, 2006, 23(2): 258-262. doi: 10.11804/NuclPhysRev.23.02.258

MCNP/MCNPX几何栅元划分方法对精确放疗剂量计算的影响研究

doi: 10.11804/NuclPhysRev.23.02.258

Effect of Different Voxel-uniting Methods on the Dose Calculation of MCNP/MCNPX

  • 摘要: 复杂几何模型的建立是Monte Carlo粒子输运程序MCNP/MCNPX在放疗领域广泛应用的关键与难点,发展了基于医学CT影像的MCNP/MCNPX自动建模软件,提出并实现了3种几何栅元划分的方法。根据临床实例数据,分别建立了3种MCNP几何模型。在此基础上,研究分析了3种几何栅元划分方法及重复结构描述方法对计算结果的影响,为MCNP/MCNPX在放疗中的应用提供基础。The key problem for the application of the Monte Carlo particle transport code MCNP/MCNPX in radiotherapy is the creation of complex geometrical model. To handle this problem, a software has been developed to automatically create MCNP/MCNPX geometrical model based on the CT images, and three geometric cell treatment schemes were proposed and implemented in this software. In this work, three MCNP models are created, and calculations are performed to investigate the effect of those cell treatment schemes and repeated structure technique on the calculation results.
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出版历程
  • 收稿日期:  1900-01-01
  • 修回日期:  1900-01-01
  • 刊出日期:  2006-06-20

MCNP/MCNPX几何栅元划分方法对精确放疗剂量计算的影响研究

doi: 10.11804/NuclPhysRev.23.02.258

摘要: 复杂几何模型的建立是Monte Carlo粒子输运程序MCNP/MCNPX在放疗领域广泛应用的关键与难点,发展了基于医学CT影像的MCNP/MCNPX自动建模软件,提出并实现了3种几何栅元划分的方法。根据临床实例数据,分别建立了3种MCNP几何模型。在此基础上,研究分析了3种几何栅元划分方法及重复结构描述方法对计算结果的影响,为MCNP/MCNPX在放疗中的应用提供基础。The key problem for the application of the Monte Carlo particle transport code MCNP/MCNPX in radiotherapy is the creation of complex geometrical model. To handle this problem, a software has been developed to automatically create MCNP/MCNPX geometrical model based on the CT images, and three geometric cell treatment schemes were proposed and implemented in this software. In this work, three MCNP models are created, and calculations are performed to investigate the effect of those cell treatment schemes and repeated structure technique on the calculation results.

English Abstract

赵攀, 陈义学, 林辉, 郑善良, 吴宜灿. MCNP/MCNPX几何栅元划分方法对精确放疗剂量计算的影响研究[J]. 原子核物理评论, 2006, 23(2): 258-262. doi: 10.11804/NuclPhysRev.23.02.258
引用本文: 赵攀, 陈义学, 林辉, 郑善良, 吴宜灿. MCNP/MCNPX几何栅元划分方法对精确放疗剂量计算的影响研究[J]. 原子核物理评论, 2006, 23(2): 258-262. doi: 10.11804/NuclPhysRev.23.02.258
ZHAO Pan, CHEN Yi-xue, LIN Hui, ZHENG Shan-liang, WU Yi-can. Effect of Different Voxel-uniting Methods on the Dose Calculation of MCNP/MCNPX[J]. Nuclear Physics Review, 2006, 23(2): 258-262. doi: 10.11804/NuclPhysRev.23.02.258
Citation: ZHAO Pan, CHEN Yi-xue, LIN Hui, ZHENG Shan-liang, WU Yi-can. Effect of Different Voxel-uniting Methods on the Dose Calculation of MCNP/MCNPX[J]. Nuclear Physics Review, 2006, 23(2): 258-262. doi: 10.11804/NuclPhysRev.23.02.258

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