Zabihzadeh Mansour, Ay Mohammad Reza, Allahverdi Mahmoud, Mesbahi Asghar, Mahdavi Seyed Rabee, Shahriari Majid
Department of Medical Physics and Biomedical Engineering, Tehran University of Medical Sciences, Tehran, Iran.
Radiat Prot Dosimetry. 2009 Jul;135(1):21-32. doi: 10.1093/rpd/ncp097. Epub 2009 May 30.
Despite all advantages associated with high-energy radiotherapy to improve therapeutic gain, the production of photoneutron via interaction of high-energy photons with high atomic number (Z) materials increases undesired dose to the patient and staff. Owing to the limitation and complication of experimental neutron dosimetry in mixed beam environment, including photon and neutron, the Monte Carlo (MC) simulation is a gold standard method for calculation of photoneutron contaminations. On the other hand, the complexity of treatment head makes the MC simulation more difficult and time-consuming. In this study, the possibility of using a simplified MC model for the simulation of treatment head has been investigated using MCNP4C general purpose MC code. As a part of comparative assessment strategy, the fluence, average energy and dose equivalent of photoneutrons were estimated and compared with other studies for several fields and energies at different points in treatment room and maze. The mean energy of photoneutrons was 0.17, 0.19 and 0.2 MeV at the patient plan for 10, 15 and 18 MeV, respectively. The calculated values differed, respectively, by a factor of 1.4, 0.7 and 0.61 compared with the reported measured data for 10, 15 and 18 MeV. Our simulation results in the maze showed that the neutron dose equivalent is attenuated by a factor of 10 for every 4.6 m of maze length while the related factor from Kersey analytical method is 5 m. The neutron dose equivalent was 4.1 mSv Gy(-1) at the isocentre and decreased to 0.79 mSv Gy(-1) at a distance of 100 cm away from the isocentre for 40 x 40 cm(2). There is good agreement between the data calculated using simplified model in this study and measurements. Considering the reported high uncertainties (up to 50%) in experimental neutron dosimetry, it can be concluded that the simplified model can be used as a useful tool for estimation of photoneutron contamination associated with high-energy photon radiotherapy.
尽管高能放射疗法在提高治疗增益方面具有诸多优势,但高能光子与高原子序数(Z)材料相互作用产生的光中子会增加患者和工作人员所受的不必要剂量。由于在包括光子和中子的混合束环境中进行实验中子剂量测定存在局限性和复杂性,蒙特卡罗(MC)模拟是计算光中子污染的金标准方法。另一方面,治疗头的复杂性使得MC模拟更加困难且耗时。在本研究中,使用MCNP4C通用MC代码研究了使用简化MC模型模拟治疗头的可能性。作为比较评估策略的一部分,估算了治疗室和迷宫中不同位置多个射野和能量下光中子的注量、平均能量和剂量当量,并与其他研究进行了比较。在患者计划中,10、15和18 MeV时光中子的平均能量分别为0.17、0.19和0.2 MeV。与报道的10、15和18 MeV的测量数据相比,计算值分别相差1.4、0.7和0.61倍。我们在迷宫中的模拟结果表明,迷宫长度每增加4.6 m,中子剂量当量衰减10倍,而克尔西分析方法的相关系数为5 m。对于40×40 cm²的射野,等中心处的中子剂量当量为4.1 mSv Gy⁻¹,在距等中心100 cm处降至0.79 mSv Gy⁻¹。本研究中使用简化模型计算的数据与测量结果吻合良好。考虑到实验中子剂量测定中报道的高不确定性(高达50%),可以得出结论,简化模型可作为估算高能光子放射疗法相关光中子污染的有用工具。