Optimization of Attila4MC Mesh Parameters in Large-scale Models for Nuclear Decommissioning Planning.

IF 1.4 4区 医学 Q4 ENVIRONMENTAL SCIENCES
Justina A M Freilich, Camille J Palmer
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引用次数: 0

Abstract

The anticipated increase in nuclear decommissioning in the coming decades requires innovative approaches to maintain worker exposure as low as reasonably achievable. Occupational dose, an important component of cost-benefit analysis and work planning in decommissioning, can be estimated using radiation transport codes. Monte Carlo N-Particle (MCNP) is a robust, well-established code that has been used to model a breadth of geometries and source terms. Attila4MC offers a graphical user interface for users to build and run MCNP simulations and create an unstructured mesh of computer-aided design (CAD) models with tunable meshing parameters, including element edge length bounds and curvature refinement features. To understand how these parameters might be optimized for a large-scale model for dose estimation, a building containing gloveboxes, a hot cell, ventilation, robotic characterization tools, and operators was modeled in a CAD program. Source terms from available literature were applied to the equipment, and the operator dose was tracked for several exposure geometries. Mesh parameters, including maximum edge length (MEL) bounds, curvature refinement part selection, d/h ratio, and minimum edge length, were varied, and the resulting dose estimates were compared. The upper MEL bound had little effect on the estimated dose rate, but the varying the lower bound resulted in a 40% change in dose rate compared to the default case. Curvature refinement increased the MCNP figure of merit very slightly, about 2.6% when applied globally, but increased by over 31% when applied to only selected parts within the model. Both minimum edge length and d/h ratio showed a maximum change in dose rate of 10% compared to the default case for the values investigated in this study. Finally, the dose rate results suggest that the use of robotic or remote characterization methods may reduce occupational dose to workers by several orders of magnitude for the modeled scenario.

核退役规划大尺度模型Attila4MC网格参数优化
未来几十年预计将增加的核退役需要创新的方法来保持工人的接触尽可能低。职业剂量是退役过程中成本效益分析和工作规划的一个重要组成部分,可使用辐射传输代码进行估算。蒙特卡罗n粒子(MCNP)是一个强大的,完善的代码,已被用于模拟几何形状和源项的广度。Attila4MC为用户提供了一个图形用户界面,用于构建和运行MCNP模拟,并创建具有可调网格参数的计算机辅助设计(CAD)模型的非结构化网格,包括元素边缘长度界限和曲率细化特征。为了了解这些参数如何为剂量估计的大规模模型进行优化,在CAD程序中对一个包含手套箱、热室、通风、机器人表征工具和操作人员的建筑物进行了建模。将现有文献中的源项应用于设备,并对几个暴露几何形状的操作人员剂量进行了跟踪。网格参数,包括最大边缘长度(MEL)边界,曲率细化部分选择,d/h比和最小边缘长度,变化,并得到的剂量估计进行比较。MEL上限对估计剂量率几乎没有影响,但与默认情况相比,下限的变化导致剂量率变化40%。曲率细化对MCNP优值的提高幅度非常小,在全球范围内应用时约为2.6%,但在仅应用于模型内选定部件时增加了31%以上。最小边缘长度和d/h比均显示,与本研究中所调查值的默认情况相比,剂量率的最大变化为10%。最后,剂量率结果表明,在模拟情景中,使用机器人或远程表征方法可将工人的职业剂量降低几个数量级。
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
Health physics
Health physics 医学-公共卫生、环境卫生与职业卫生
CiteScore
4.20
自引率
0.00%
发文量
324
审稿时长
3-8 weeks
期刊介绍: Health Physics, first published in 1958, provides the latest research to a wide variety of radiation safety professionals including health physicists, nuclear chemists, medical physicists, and radiation safety officers with interests in nuclear and radiation science. The Journal allows professionals in these and other disciplines in science and engineering to stay on the cutting edge of scientific and technological advances in the field of radiation safety. The Journal publishes original papers, technical notes, articles on advances in practical applications, editorials, and correspondence. Journal articles report on the latest findings in theoretical, practical, and applied disciplines of epidemiology and radiation effects, radiation biology and radiation science, radiation ecology, and related fields.
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