| 纪刚,郭勇,骆亿生,等.252Cf裂变中子源在组织等效模体中的中子和γ辐射剂量分布的计算[J].中华放射医学与防护杂志,2001,21(4):244-246.JI Gang,GUO Yong,LUO Yisheng,et al.Calculation of dose distribution for 252Cf fission neutron source in tissue equivalent phantoms using Monte Carlo method[J].Chin J Radiol Med Prot,2001,21(4):244-246 |
| 252Cf裂变中子源在组织等效模体中的中子和γ辐射剂量分布的计算 |
| Calculation of dose distribution for 252Cf fission neutron source in tissue equivalent phantoms using Monte Carlo method |
| 投稿时间：2001-04-30 |
| DOI： |
| 中文关键词: 252Cf裂变中子源 蒙特卡罗计算 剂量分布 组织等效模体 |
| 英文关键词:252Cf fission neutron source Monte Carlo Dose distribution Tissue equivalent phantom |
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| 中文摘要: |
| 目的 计算252Cf裂变中子源的中子和γ辐射在组织等效模体内的剂量分布,为使用252Cf裂变中子源进行中子放疗提供有用的剂量学参数.方法 建立252Cf源和组织等效模体的三维几何计算模型,利用蒙特卡罗方法进行中子和γ辐射联合输运计算.结果 计算了两种医用252Cf裂变中子源在水、血液、肌肉、皮肤、骨骼和肺组织等效材料构成的模体中距源不同距离点处的中子和γ辐射吸收剂量.结论 蒙特卡罗计算结果与文献数据以及使用双电离室实验测量的结果符合得较好.对252Cf裂变中子源在 5种组织材料构成的模体中中子和γ辐射的剂量分布进行了比较,使用水作为组织等效材料对252Cf裂变中子源在以肌肉、血液和皮肤构成的局部组织内的剂量分布进行模拟计算,可取得比较可靠的结果. |
| 英文摘要: |
| 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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