跨铀污染特征描述远程方法中 MCNP 和微屏蔽剂量节省测定的比较。

IF 1 4区 医学 Q4 ENVIRONMENTAL SCIENCES
Health physics Pub Date : 2024-10-01 Epub Date: 2024-05-26 DOI:10.1097/HP.0000000000001829
Justina A M Freilich, Camille J Palmer
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引用次数: 0

摘要

机器人和远程系统的成熟为将通常仅限于高剂量/高风险核工作的技术扩大用于中度或低风险工作提供了机会,从而进一步减少工人受到的辐射照射。本研究量化了通过使用机器人技术表征受跨铀污染的废物物项而实现的潜在剂量节省,并比较了来自简单、用户友好的确定性辐射传输代码和更强大、更复杂的蒙特卡洛代码的剂量估计值。利用微屏蔽和 MCNP 辐射传输代码中具有代表性的源几何形状,对已发表报告中描述的三种受超铀污染的废物进行建模。估算的剂量率是在距离废物表面 30 厘米到 300 厘米之间的点上确定的,以表示机器人或远程系统实施特征描述活动时允许增加的距离。然后,使用美元/人剂量转换系数将节省的剂量率转换为节省的损害成本,以提供财务背景。辐射传输模拟表明,不同的模拟方法或使用几何简化方法对估计剂量率的偏差并不一致--在某些情况下,微护盾得出的估计剂量率更高,而在其他情况下,MCNP 得出的估计剂量率更高。在 MCNP 模拟中,体积源几何形状产生的剂量率始终高于板状源几何形状,但 MicroShield 的剂量率估计值没有显示出相同的趋势。节省的剂量从 1.60 × 10-5 μSv h-1 到 1.75 × 101 μSv h-1 不等,节省的相关损害成本从 < 0.010 美元/人-小时到 14 美元/人-小时不等。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Comparison of MCNP and Microshield Dose Savings Determinations for Remote Methods of Transuranic Contamination Characterization.

The maturation of robotic and remote systems presents opportunities to expand the use of technologies that have typically been restricted to high-dose/high-risk nuclear work for moderate- or low-risk work to further reduce radiation exposure to workers. This study quantifies the potential dose savings achieved through the use of robotic techniques for characterizing transuranic-contaminated waste items and compares dose estimates from a simplistic, user-friendly deterministic radiation transport code and a more robust, complex Monte Carlo code. Three scenarios of transuranic-contaminated waste items described in published reports are modeled using representative source geometries in MicroShield and MCNP radiation transport codes. Estimated dose rates are determined at points ranging from 30 cm to 300 cm from the face of the waste item to represent the increase in distance allowed by robotic or remote system implementation for characterization activities. The dose rate savings are then converted to detriment cost savings using a dollar-per-person-dose conversion factor to provide a financial context. The radiation transport simulations show no consistent bias in estimated dose rate by varying simulation methodology or using geometrical simplifications-in some cases, MicroShield produces higher dose rate estimates while MCNP estimates are higher in other cases. In the MCNP simulations, the volume source geometry consistently produces a higher dose rate than the slab source geometry, but the MicroShield dose rate estimates do not display the same trend. Dose savings range from 1.60 × 10-5 μSv h-1 to 1.75 × 101 μSv h-1 with associated detriment cost savings from < 0.010 USD/person-h to 14 USD/person-h.

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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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