Evaluation of the KERMA approximation method in Monte Carlo dose calculations for BNCT involving a realistic 3D patient phantom.

IF 0.8 4区 环境科学与生态学 Q4 ENVIRONMENTAL SCIENCES
Meitong Wei, Yuxin Wang, Zirui Ye, Hui Zhang, Xie George Xu
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引用次数: 0

Abstract

Monte Carlo (MC) methods are generally recognized as the gold standard for dose calculations. However, achieving high statistical confidence is computationally expensive, particularly when complex secondary particles are involved. Kinetic Energy Released in Matter (KERMA) approximation method is a variance reduction technique widely used in MC simulations. This study evaluated the accuracy and efficiency of the KERMA approximation for Boron Neutron Capture Therapy (BNCT) dose calculations using the TOol for PArticle Simulation MC code. Simulations were performed on a CT phantom of a glioblastoma patient using an accelerator-based BNCT source. It was found that neutron KERMA results agreed with Analog MC results within 2%, while providing a 157-fold computational speed-up. However, the photon KERMA approximation overestimated skin photon dose by ~12%. The results suggest that the KERMA approximation for BNCT offers clinically acceptable accuracy and efficiency, while using Analog MC method for skin photon dose evaluation can further improve overall accuracy.

评估KERMA近似方法在蒙特卡罗剂量计算BNCT涉及一个现实的三维病人幻影。
蒙特卡罗(MC)方法通常被认为是剂量计算的金标准。然而,实现高统计置信度在计算上是昂贵的,特别是当涉及复杂的二次粒子时。物质释放动能(KERMA)近似法是一种广泛应用于MC模拟的方差缩减技术。本研究利用粒子模拟工具MC代码对硼中子捕获疗法(BNCT)剂量计算的KERMA近似的准确性和效率进行了评估。使用基于加速器的BNCT源对胶质母细胞瘤患者的CT幻像进行模拟。发现中子KERMA结果与模拟MC结果的一致性在2%以内,同时提供了157倍的计算速度。然而,光子KERMA近似将皮肤光子剂量高估了约12%。结果表明,KERMA近似用于BNCT具有临床可接受的准确性和效率,而使用Analog MC方法进行皮肤光子剂量评估可以进一步提高整体准确性。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Radiation protection dosimetry
Radiation protection dosimetry 环境科学-公共卫生、环境卫生与职业卫生
CiteScore
1.40
自引率
10.00%
发文量
223
审稿时长
6-12 weeks
期刊介绍: Radiation Protection Dosimetry covers all aspects of personal and environmental dosimetry and monitoring, for both ionising and non-ionising radiations. This includes biological aspects, physical concepts, biophysical dosimetry, external and internal personal dosimetry and monitoring, environmental and workplace monitoring, accident dosimetry, and dosimetry related to the protection of patients. Particular emphasis is placed on papers covering the fundamentals of dosimetry; units, radiation quantities and conversion factors. Papers covering archaeological dating are included only if the fundamental measurement method or technique, such as thermoluminescence, has direct application to personal dosimetry measurements. Papers covering the dosimetric aspects of radon or other naturally occurring radioactive materials and low level radiation are included. Animal experiments and ecological sample measurements are not included unless there is a significant relevant content reason.
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