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Assessing the Mental Model State of Emergency Responders in the Context of Radiological Dispersal Device (RDD) Incidents: A Multi-state Study. 评估辐射散布装置 (RDD) 事件背景下应急响应人员的心理模式状态:多州研究。
IF 1 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-07-25 DOI: 10.1097/HP.0000000000001856
Angela E Leek, Nir Keren, Mack C Shelley, Warren Franke, Gretchen A Mosher, Stephen A Simpson, Timothy Rice, H Emily Hayden

Abstract: Hazardous Materials (HAZMAT) Technicians' notions of mental model, or cognitive representations of their understanding and beliefs regarding Radiological Dispersal Devices (RDDs) incidents, have not been previously explored. A prior study developed an Expected Mental Model State (EMMS) framework specific to RDD incident response for HAZMAT technicians. The work herein presents the development of a derivative of this framework, the EMMS Diagnostic Matrix, to evaluate the actual Mental Model State (MMS) of HAZMAT technicians in the context of RDD incidents. The EMMS Diagnostic Matrix was administered via a survey and simulation activity in four U.S. states representing the Northeast, West, South, and Midwest regions. Data were collected and coded using grounded theory methodology. Reflexive thematic analysis was employed to identify themes across related areas where the notions of mental model for the HAZMAT technician responders' actual MMS differed from the EMMS. The analysis of the collected data revealed four significant themes representing incomplete notions of the mental model spanning various EMMS conceptual domains: Overestimation of Radiation Dose and Health Effects, indicating misunderstandings about the health impacts of radiation exposure, Acute Radiation Syndrome (ARS), particularly in the lower range of radiation doses; Overreliance on Responder Protection [personal protective equipment (PPE)/self-contained breathing apparatus (SCBA)], highlighting gaps in understanding radiation principles and radioactive material dispersal properties from a radiological dispersal device; Misunderstanding Radiation Detection and Units, signifying confusion about radiation units and differentiation between dose rate and accumulated dose; and Incomplete Understanding of Radiation Characteristics and Dispersal Properties, outlining a limited grasp of inhalation risks from radiation and the dispersal traits of a radiological dispersal device. The interconnectedness of these technical misunderstandings can guide the development of a strategic plan to evaluate and modify existing training, aiming at these specific themes to improve the efficiency of HAZMAT technicians in emergency situations and to identify areas for further research.

摘要:危险材料(HAZMAT)技术人员的心智模式概念,即他们对放射性物质扩散装置(RDDs)事件的理解和信念的认知表征,此前尚未进行过探讨。之前的一项研究为危险品运输 (HAZMAT) 技术人员开发了一个专门针对 RDD 事件响应的预期心智模式状态 (EMMS) 框架。本文介绍了该框架的衍生工具--"EMMS 诊断矩阵 "的开发情况,以评估危险品、有害物质和弹药技术人员在 RDD 事件中的实际心理模型状态 (MMS)。EMMS 诊断矩阵通过调查和模拟活动在美国东北部、西部、南部和中西部地区的四个州实施。采用基础理论方法收集数据并进行编码。采用了反思性主题分析法来确定相关领域的主题,在这些领域中,危险品运输技术人员的实际 MMS 心智模式概念与 EMMS 存在差异。通过对收集到的数据进行分析,发现了四个重要的主题,它们代表了心智模式的不完整概念,跨越了环境监测管理系统的各个概念领域:高估辐射剂量和对健康的影响,表明对辐射照射、急性辐射综合症(ARS)对健康的影响存在误解,尤其是在较低的辐射剂量范围内;过度依赖响应者防护[个人防护设备(PPE)/自给式呼吸器(SCBA)],突出表明在理解辐射原理和放射性物质从放射性物质散布装置中散布的特性方面存在差距;对辐射检测和单位的误解,表明对辐射单位以及剂量率和累积剂量之间区别的混淆;以及对辐射特征和散布特性的不完全理解,概述了对辐射吸入风险和放射性散布装置散布特性的有限掌握。这些技术误解之间的相互联系可以指导制定一项战略计划,以评估和修改现有培训,针对这些特定主题提高危险品、有害物质和弹药技术人员在紧急情况下的效率,并确定进一步研究的领域。
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引用次数: 0
Minimum Detectable Intakes and Doses for Uranium Bioassays-Comparison between Alpha Spectrometry and ICP-MS. 铀生物测定的最小可检测摄入量和剂量--阿尔法光谱法与 ICP-MS 的比较。
IF 1 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-07-25 DOI: 10.1097/HP.0000000000001854
B Rosenberg, A Johnson, C G Potter, C L Antonio

Abstract: Naturally occurring uranium complicates monitoring for occupational exposures. There are several retroactive methods that can be used to monitor for occupational exposures, with benefits and drawbacks to each. Analysis of uranium in urine by mass spectrometry and alpha spectrometry is compared, and methods of determining an occupational exposure are presented. The minimum detectable concentrations from each analysis and a method for intake determination based on the analytical results are compared for various solubility types and mixtures. Mass spectrometry with radiochemical separation was found to be the most sensitive analysis for detecting occupational exposures to anthropogenic mixtures based on minimum detectable doses calculated from the proposed method for intake determination.

摘要:天然存在的铀使职业暴露监测变得复杂。有几种可用于监测职业暴露的追溯方法,每种方法都有优点和缺点。本文比较了质谱法和阿尔法光谱法对尿液中铀的分析,并介绍了确定职业接触的方法。比较了每种分析方法的最低检测浓度,以及根据各种溶解类型和混合物的分析结果确定摄入量的方法。根据拟议的摄入量确定方法计算出的最低检测剂量,发现在检测人为混合物的职业接触方面,带有放射化学分离的质谱法是最灵敏的分析方法。
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引用次数: 0
Modeling Plutonium Decorporation in a Female Nuclear Worker Treated with Ca-DTPA after Inhalation Intake. 模拟一名女核电工人在吸入 Ca-DTPA 后体内的钚分解。
IF 1 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-07-22 DOI: 10.1097/HP.0000000000001859
Sara Dumit, Maia Avtandilashvili, Stacey L McComish, Guthrie Miller, Jasen Swanson, Sergey Y Tolmachev

Abstract: The present work models plutonium (Pu) biokinetics in a female former nuclear worker. Her bioassay measurements are available at the US Transuranium and Uranium Registries. The worker was internally exposed to a plutonium-americium mixture via acute inhalation at a nuclear weapons facility. She was medically treated with injections of 1 g Ca-DTPA on days 0, 5, and 14 after the intake. Between days 0 and 20, fecal and urine samples were collected and analyzed for 239Pu and 241Am. Subsequently, she was followed up for bioassay monitoring over 14 y, with additional post-treatment urine samples collected and analyzed for 239Pu. The uniqueness of this dataset is due to the availability of: (1) both early and long-term bioassay data from a female with plutonium intake; (2) data on chelation therapy for a female; and (3) fecal measurement results. Chelation therapy with Ca- and/or Zn-salts of DTPA is known to aid in reducing the internal radiation dose by enhancing the excretion of plutonium and americium from the body. Such enhancement affects plutonium biokinetics in the human body, posing a challenge to the internal dose assessment. The current radiation dose assessment practice is to exclude the data affected by Ca-DTPA from the analysis. The present analysis is the first to explicitly model the chelation-affected bioassay data in a female by using a newly developed chelation model. Thus, the bioassay data collected during and after the Ca-DTPA administrations were used for biokinetic modeling and dose assessment. The Markov Chain Monte Carlo method was used to investigate model parameter uncertainty, based on the bioassay data and assumed prior probability distributions. A χ2/nData (number of data points) ≈ 1 was observed in this study, which indicates self-consistency of the data with the model. Results of this study show that the worker's 239Pu intake was 12 Bq, with a committed effective dose to the whole-body of 1.2 mSv and a committed equivalent dose to the bone surfaces, liver, and lungs of 37.8, 9.1, and 0.8 mSv, respectively. This study also discusses the worker's dose reduction due to chelation treatment.

摘要:本研究建立了一名女性前核电工人的钚(Pu)生物动力学模型。她的生物测定结果可从美国铀和铀登记处获得。该工人曾在一个核武器设施中通过急性吸入钚镅混合物而受到内照射。在吸入后的第 0、5 和 14 天,她接受了注射 1 克 Ca-DTPA 的药物治疗。在第 0 天至第 20 天期间,收集了粪便和尿液样本,并对其进行了 239Pu 和 241Am 分析。随后,对她进行了 14 年的生物测定监测随访,并收集了更多的治疗后尿液样本,对其进行 239Pu 分析。该数据集的独特之处在于:(1) 一名摄入钚的女性的早期和长期生物测定数据;(2) 一名女性的螯合疗法数据;(3) 粪便测量结果。众所周知,使用 DTPA 的钙盐和/或锌盐进行螯合治疗,可以通过促进体内钚和镅的排泄来帮助减少体内辐射剂量。这种增强作用会影响钚在人体内的生物动力学,对体内剂量评估构成挑战。目前的辐射剂量评估做法是将受 Ca-DTPA 影响的数据排除在分析之外。本分析首次使用新开发的螯合模型,明确模拟受螯合影响的女性生物测定数据。因此,在服用 Ca-DTPA 期间和之后收集的生物测定数据被用于生物动力学建模和剂量评估。根据生物测定数据和假定的先验概率分布,采用马尔可夫链蒙特卡洛法研究了模型参数的不确定性。本研究观察到 χ2/nData(数据点数)≈ 1,这表明数据与模型是自洽的。研究结果显示,该工人的 239Pu 摄入量为 12 Bq,全身的承诺有效剂量为 1.2 mSv,骨面、肝脏和肺部的承诺当量剂量分别为 37.8、9.1 和 0.8 mSv。该研究还讨论了工人因螯合治疗而减少的剂量。
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引用次数: 0
Regional Workshop on Optimization of Protection in Pediatric Interventional Radiology in Latin American and Caribbean Countries. 拉丁美洲和加勒比国家儿科介入放射学保护优化区域研讨会。
IF 1 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-07-08 DOI: 10.1097/HP.0000000000001850
Carlos Ubeda, Eliseo Vano, María Del Rosario Perez, Raúl Ramirez, Alejandro Nader, Patricia Miranda, José Miguel Fernandez, Mar Pérez-Peña

Abstract: The purpose of this article is to describe the activities developed within the framework "Regional Workshop on Optimization of Protection in Pediatric Interventional Radiology in Latin American and Caribbean countries," developed between October 16th and 19th of the year 2023 in the city of San José, Costa Rica. The workshop was carried out as part of a joint work between the Pan American Health Organization (PAHO) and the World Health Organization (WHO), in cooperation with the International Atomic Energy Agency (IAEA). The main objective of the regional workshop was to gather the experiences and future work planning among participants in the Optimization of Protection in Pediatric Interventional Radiology in Latin America and the Caribbean (OPRIPALC) program. It involved professionals from 14 centers across 11 countries in the region, along with 4 experts from PAHO/WHO/IAEA. The work modalities during the workshop consisted of keynote presentations, individual presentations, group work, and general discussions. An online survey was carried out after the workshop, with the objective of knowing the opinion of the event participants and determining the impact and projection of the OPRIPALC program. During the workshop the centers had to present their experiences: the use of the DOLQA dose management system was presented and work was done on the consensus document on good practices. The activities, topics and organization of the workshop were valued positively by the participants. There is unanimity among the centers that the OPRIPALC program has had a positive impact and they wish to continue actively participating in the next biennium.

摘要:本文旨在介绍 2023 年 10 月 16 日至 19 日在哥斯达黎加圣何塞市举办的 "拉丁美洲和加勒比国家儿科介入放射学保护优化区域研讨会 "框架内开展的活动。该讲习班是泛美卫生组织(PAHO)和世界卫生组织(WHO)与国际原子能机构(IAEA)合作开展的一项联合工作的一部分。该地区研讨会的主要目的是收集拉丁美洲和加勒比地区儿科介入放射学优化保护计划(OPRIPALC)参与者的经验和未来工作规划。来自该地区 11 个国家 14 个中心的专业人员以及泛美卫生组织/世界卫生组织/国际原子能机构的 4 名专家参加了此次研讨会。研讨会期间的工作方式包括主旨发言、个人发言、小组工作和一般性讨论。讲习班结束后进行了在线调查,目的是了解与会者的意见,确定 OPRIPALC 计划的影响和预测。在讲习班期间,各中心必须介绍其经验:介绍 DOLQA 剂量管理系统的使用情况,并就良好做法的共识文件开展工作。与会者对讲习班的活动、主题和组织工作给予了积极评价。各中心一致认为,OPRIPALC 计划产生了积极影响,希望在下一个双年度继续积极参与。
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引用次数: 0
The Concentration of Uranium-238 in Soil Samples from the Central Maysan Governorate Determined Using ICP-MS. 使用 ICP-MS 测定中部迈桑省土壤样本中铀-238 的浓度。
IF 1 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-07-05 DOI: 10.1097/HP.0000000000001846
Anaheed Ahmed, Thaer M Salman, Mostafa A Algrifi

Abstract: In this particular investigation, 30 surface soil samples taken from various locations across the Middle Omara governorate in southeastern Iraq were analyzed using ICP-MS (inductively coupled plasma mass spectrometry), and several of these, as far as the researchers know, had never been analyzed previously. The results are presented and compared with those from a different study. The studied soil samples had <100 ppm of uranium, which shows they are composed of overloads and garbage rather than mineable stocks. This article describes and assesses the uranium content in the Middle Omara Governorates. Additionally, all 30 exposed earth samples had uranium below the detection threshold. The results show that the samples of surface soils under investigation have uranium concentrations below the permissible maximum (11.7 ppm) established by UNSCEAR in 1993.

摘要:在这项特别调查中,使用 ICP-MS(电感耦合等离子体质谱法)分析了从伊拉克东南部 Middle Omara 省不同地点采集的 30 个表层土壤样本,据研究人员所知,其中有几个样本以前从未分析过。本文介绍了分析结果,并将其与另一项研究的结果进行了比较。所研究的土壤样本具有
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引用次数: 0
An Estimation of the Monetary Value of the Person-Sievert Useful for Occupational Radiological Protection within the Healthcare System of Sweden. 对瑞典医疗保健系统内用于职业辐射防护的人-西弗特货币价值的估算。
IF 1 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-06-21 DOI: 10.1097/HP.0000000000001848
Andreas Engström, Mats Isaksson, Reza Javid, Per-Anders Larsson, Charlotta Lundh, Magnus Båth

Abstract: The As Low As Reasonably Achievable (ALARA) principle includes taking into account economic and societal factors. To consider these factors, decision-aiding techniques such as cost-benefit analysis were introduced by the International Commission on Radiological Protection (ICRP) 50 y ago. Over the years, developments in health economics have led to new ways of deriving the concept of a value of a statistical life (VSL), which now is influencing the monetary value assigned to a unit of collective dose for radiological protection purposes (the α value) used in cost-benefit analyses. The aim of the present study was to estimate an α value useful for occupational radiological protection within the healthcare system of Sweden. A survey based on the stated preference approach was developed and sent to staff who are exposed to ionizing radiation at their work in Region Västra Götaland (Sweden). The survey essentially contained two scenarios: the respondents' willingness to pay for measures against radon exposure at home and their willingness to accept compensation for x-ray exposure at work. Answers from 718 respondents were collected. In the sensitivity analysis of the survey, the overall median VSL based on the two scenarios was calculated to be $50 million (IQR $10 to 363 million). The corresponding α value was established to $1,600 person-mSv -1 ($2,100 person-mSv -1 if excess burden of taxes is excluded). The recommended α value is in the high end compared to other studies but within the interval of values being used by nuclear utilities today. The α value should be seen in the light of ICRP's recommendation about stakeholder involvement as an important part of the optimization process.

摘要:"尽可能合理地低"(ALARA)原则包括考虑经济和社会因素。为了考虑这些因素,国际辐射防护委员会(ICRP)在 50 年前引入了成本效益分析等辅助决策技术。多年来,健康经济学的发展带来了推导统计寿命值(VSL)概念的新方法,而统计寿命值现在正影响着成本效益分析中用于辐射防护的单位集体剂量的货币价值(α 值)。本研究的目的是估算出瑞典医疗系统中用于职业辐射防护的 α 值。研究人员根据陈述偏好法编制了一份调查表,并将其发送给瑞典 Västra Götaland 地区在工作中暴露于电离辐射的工作人员。调查主要包括两种情况:受访者是否愿意为家中的氡照射措施付费,以及是否愿意接受工作中的 X 射线照射补偿。共收集到 718 位受访者的回答。在对调查进行的敏感性分析中,根据这两种情况计算出的总体自愿赔偿额中值为 5,000 万美元(IQR 为 1,000 万至 3.63 亿美元)。相应的 α 值被确定为 1,600 美元/人-mSv-1(如果不考虑超额税收负担,则为 2,100 美元/人-mSv-1)。与其他研究相比,建议的 α 值偏高,但在目前核设施使用的数值范围内。在看待 α 值时,应考虑到国际辐射防护委员会的建议,即利益相关者的参与是优化过程的重要组成部分。
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引用次数: 0
Prediction Model for Defects in Lead and Lead-free Aprons. 铅和无铅围裙缺陷预测模型。
IF 2.2 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-06-17 DOI: 10.1097/HP.0000000000001847
Pieter-Jan Kellens, An De Hauwere, Sandrine Bayart, Klaus Bacher, Tom Loeys

Abstract: Personal radiation protective equipment (PRPE) is prone to defects in the attenuating layers, resulting in inadequate protection. Hence, quality control (QC) of PRPE is needed to assess its integrity. Unfortunately, QC of PRPE is laborious and time consuming. This study aimed to predict the QC outcome of PRPE without x-ray imaging based on readily available predictors. PRPE QC data of a general hospital from 2018 to 2023 was used for both prediction models based on logistic regression and random forests (RF). The data were divided into a training set containing all data from 2018 to 2022 and a holdout set containing the data from 2023. The predictors were brand, age, size, type, visual defects, and department. The prediction performances were compared using confusion matrices and visualized with receiver operating characteristic (ROC) curves. Prediction accuracies of at least 80% were achieved. Further model tuning especially improved the RF model to a precision up to 97% with a sensitivity of 80% and specificity of 86%. All predictors, except visual defects, significantly impacted the probability of passing. The predictor brand had the largest contribution to the predictive performance. The difference in pass probability between the best-performing and the worst-performing brand was 35.1%. The results highlight the potential of predicting PRPE QC outcome without x rays. The proposed prediction approach is a significant contribution to an effective QC strategy by reducing time consuming x-ray QC tests and focusing on garments with higher probability of being defective. Further research is recommended.

摘要:个人辐射防护设备(PRPE)的衰减层容易出现缺陷,导致防护效果不佳。因此,需要对 PRPE 进行质量控制 (QC),以评估其完整性。遗憾的是,PRPE 的质量控制费时费力。本研究旨在根据现成的预测指标,在没有 X 射线成像的情况下预测 PRPE 的质量控制结果。一家综合医院 2018 年至 2023 年的 PRPE QC 数据被用于基于逻辑回归和随机森林(RF)的预测模型。数据分为包含 2018 年至 2022 年所有数据的训练集和包含 2023 年数据的保留集。预测因子为品牌、年龄、大小、类型、视觉缺陷和科室。预测结果使用混淆矩阵进行比较,并通过接收器操作特征曲线(ROC)进行可视化。预测准确率至少达到了 80%。对模型的进一步调整尤其提高了 RF 模型的精确度,精确度高达 97%,灵敏度为 80%,特异度为 86%。除视觉缺陷外,所有预测因子都对通过概率有显著影响。预测因子品牌对预测性能的贡献最大。表现最好的品牌和表现最差的品牌之间的通过概率相差 35.1%。结果凸显了在没有 X 射线的情况下预测 PRPE 质量控制结果的潜力。所提出的预测方法减少了耗时的 X 射线质量控制测试,并将重点放在瑕疵概率较高的服装上,对有效的质量控制策略做出了重大贡献。建议进一步开展研究。
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引用次数: 0
Protecting Our Own: A Method for Reducing Breast Radiation Exposure in Healthcare Workers. 保护我们自己:减少医护人员乳房辐射暴露的方法》(Protecting Our Own: A Method for Reducing Breast Radiation Exposure in Healthcare Workers)。
IF 2.2 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-05-06 DOI: 10.1097/HP.0000000000001832
Lauren Zammerilla Westcott, Gerald O Ogola, Chet R Rees

Abstract: Standard lead aprons do not protect the female breast adequately from radiation exposure, which has been associated with breast cancer in healthcare workers. A novel lead shield was designed to reduce radiation to the breast, axilla, and thyroid (BAT). A procedure room was simulated with an anthropomorphic phantom representing the operator. Dosimeters were positioned on the outer quadrant of each breast, the chest, the thyroid, and deep inside of a phantom acrylic female torso with neck and head. Standard lead vest plus a thyroid shield was used as control and compared to standard lead vest plus BAT shield. Three operator and two image receptor positions were tested. The reductions in radiation exposure were calculated. The standard vest plus BAT shield provided significant reductions in radiation exposure for all anatomic locations compared to control. When averaging all operator positions, the BAT provided reductions of 91% (p < 0.0001) for near breast. Reductions for far breast, chest, thyroid, and deep tissues were 76% (p = 0.016), 94% (p < 0.0001), 52% (p = 0.026), and 60% (p = 0.004). With operator 90° to the table using a cross-table lateral beam, the BAT provided a 97.7% reduction in radiation to the near breast and significant reduction in radiation to the chest, thyroid, and deep tissues. The BAT shield reduces radiation exposure to the breast, chest, thyroid and deep hematopoietic tissues. Such shields could benefit healthcare workers to reduce the risk of breast cancer and other radiation-associated cancers.

摘要:标准的铅围裙不能充分保护女性乳房免受辐射照射,而辐射照射与医护人员患乳腺癌有关。为了减少乳房、腋窝和甲状腺(BAT)的辐射,我们设计了一种新型铅防护罩。用一个代表操作者的拟人化模型模拟了一个手术室。剂量计被放置在每个乳房的外象限、胸部、甲状腺以及带有颈部和头部的丙烯酸女性躯干模型的内部深处。标准铅背心加甲状腺防护罩作为对照,并与标准铅背心加 BAT 防护罩进行比较。测试了三个操作员和两个图像接收器位置。计算了辐射照射的减少量。与对照组相比,标准背心加 BAT 防护罩可显著减少所有解剖位置的辐照量。如果对所有操作者位置进行平均,BAT 可使近乳房的辐射量减少 91%(p < 0.0001)。远乳房、胸部、甲状腺和深层组织的辐射量分别减少了 76% (p = 0.016)、94% (p < 0.0001)、52% (p = 0.026) 和 60% (p = 0.004)。操作者与手术台成 90°,使用跨台横向射束时,BAT 可将近处乳房的辐射减少 97.7%,并显著减少胸部、甲状腺和深部组织的辐射。BAT 防护罩可减少对乳房、胸部、甲状腺和深部造血组织的辐射照射。这种防护罩可以使医护人员受益,降低罹患乳腺癌和其他辐射相关癌症的风险。
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引用次数: 0
Neutron Activation Analysis Based on AB-BNCT Treatment Room. 基于 AB-BNCT 治疗室的中子活化分析。
IF 2.2 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-04-26 DOI: 10.1097/hp.0000000000001819
Yunzhu Cai, Shaoxian Gu, Ningyu Wang, Fengjie Cui, Wei Liu, Tianhang Li, Zhangwen Wu, Chengjun Gou
Boron neutron capture therapy (BNCT) is an ideal binary targeted radiotherapy for treating refractory tumors. An accelerator-based BNCT (AB-BNCT) neutron source has attracted more and more attention due to its advantages such as higher neutron yield in the keV energy region, less gamma radiation, and higher safety. In addition to 10B, neutrons also react with other elements in the treatment room during BNCT to produce many activation products. Due to the long half-life of some activation products, there will be residual radiation after the end of treatment and the shutdown of the accelerator, which has adverse effects on radiation workers. Therefore, the ambient dose equivalent rate in the treatment room needs to be evaluated. The AB-BNCT neutron source model proposed by Li is studied in this paper. Based on the Monte Carlo method, the Geant4 platform was used to simulate the dose induced by radionuclides near the Beam Shaping Assembly (BSA) of the source. It is concluded that the concrete wall contributed the most to the radiation dose. The dose rate of 2.45 μSv h-1 after 13 min of shutdown meets the dose rate limit of 2.5 μSv h-1, at which point it is safe for workers to enter the treatment room area.
硼中子俘获疗法(BNCT)是治疗难治性肿瘤的理想二元靶向放射疗法。基于加速器的硼中子俘获疗法(AB-BNCT)中子源因其在keV能量区具有较高的中子产率、较少的伽马辐射和较高的安全性等优点而受到越来越多的关注。除 10B 外,中子还会在 BNCT 期间与治疗室内的其他元素发生反应,产生许多活化产物。由于一些活化产物的半衰期较长,在治疗结束、加速器关闭后会有残余辐射,对辐射工作人员产生不利影响。因此,需要对治疗室的环境剂量当量率进行评估。本文研究了 Li 提出的 AB-BNCT 中子源模型。基于蒙特卡洛方法,利用 Geant4 平台模拟了放射源光束整形组件(BSA)附近放射性核素引起的剂量。结果表明,混凝土墙对辐射剂量的影响最大。关闭 13 分钟后的剂量率为 2.45 μSv h-1,符合剂量率限值 2.5 μSv h-1,此时工人进入治疗室区域是安全的。
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引用次数: 0
Consequences of Violating Conditions of Counting Statistics Are Not Severe When Measuring Radon Progeny Concentrations with the Thomas and Kusnetz Methods. 用托马斯法和库斯奈兹法测量氡子体浓度时,违反计数统计条件的后果并不严重。
IF 2.2 4区 医学 Q4 ENVIRONMENTAL SCIENCES Pub Date : 2024-04-16 DOI: 10.1097/hp.0000000000001817
Phillip H Jenkins
When analyzing samples of radon progeny using the Thomas or Kusnetz methods, we violate one of the conditions of counting statistics because we use counting times that are not short compared with the half-lives of the radionuclides. The result is that we overestimate the uncertainties of the counts if we use counting statistics without correction. In this work, I describe the method by which I adjusted the values of variance of the counts theoretically to values that are more accurate and calculated the amounts by which I overestimate the values of counting uncertainty by using counting statistics without correction. These values are surprisingly small: 4-5% for the Thomas method and 2-3% for the Kusnetz method. Now, I can correct uncertainty values of radon progeny measurements if it is appropriate to do so. The detailed calculations I present here may be used for determining corrections to the counting uncertainty for a method for measuring radon progeny concentration using different sampling and/or counting times than those described here. Further, they may be used for any sample, not necessarily radon progeny, that requires a long counting time to acquire a significant number of observed counts.
在使用托马斯或库斯耐茨方法分析氡后代样本时,我们违反了计数统计的一个条件,因为我们使用的计数时间与放射性核素的半衰期相比并不短。结果就是,如果我们使用计数统计而不进行修正,我们就会高估计数的不确定性。在这项工作中,我介绍了将理论上的计数方差值调整为更精确值的方法,并计算了在使用计数统计而不进行校正的情况下高估计数不确定度的数值。这些数值小得出奇:托马斯方法为 4-5%,库斯涅茨方法为 2-3%。现在,我可以对氡后代测量的不确定度值进行修正,如果这样做是合适的。我在这里介绍的详细计算方法可用于确定对使用与这里所述不同的取样和/或计数时间测量氡原浓度的方法的计数不确定度的修正。此外,它们还可用于任何需要较长计数时间才能获得大量观测计数的样品,不一定是氡原。
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引用次数: 0
期刊
Health physics
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