• 文献检索
  • 文档翻译
  • 深度研究
  • 学术资讯
  • Suppr Zotero 插件Zotero 插件
  • 邀请有礼
  • 套餐&价格
  • 历史记录
应用&插件
Suppr Zotero 插件Zotero 插件浏览器插件Mac 客户端Windows 客户端微信小程序
定价
高级版会员购买积分包购买API积分包
服务
文献检索文档翻译深度研究API 文档MCP 服务
关于我们
关于 Suppr公司介绍联系我们用户协议隐私条款
关注我们

Suppr 超能文献

核心技术专利:CN118964589B侵权必究
粤ICP备2023148730 号-1Suppr @ 2026

文献检索

告别复杂PubMed语法,用中文像聊天一样搜索,搜遍4000万医学文献。AI智能推荐,让科研检索更轻松。

立即免费搜索

文件翻译

保留排版,准确专业,支持PDF/Word/PPT等文件格式,支持 12+语言互译。

免费翻译文档

深度研究

AI帮你快速写综述,25分钟生成高质量综述,智能提取关键信息,辅助科研写作。

立即免费体验

核医学设施剂量计算和屏蔽设计的剂量当量率常数和势垒透射数据。

Dose equivalent rate constants and barrier transmission data for nuclear medicine facility dose calculations and shielding design.

机构信息

*Sunnybrook Research Institute, Toronto, Ontario, Canada; †Department of Medical Imaging, Sunnybrook Health Sciences Centre, Toronto, Ontario, Canada; †Departments of Medical Imaging and Medical Biophysics, University of Toronto, Toronto, Ontario, Canada.

出版信息

Health Phys. 2014 Jul;107(1):60-72. doi: 10.1097/HP.0000000000000051.

DOI:10.1097/HP.0000000000000051
PMID:24849904
Abstract

A primary goal of nuclear medicine facility design is to keep public and worker radiation doses As Low As Reasonably Achievable (ALARA). To estimate dose and shielding requirements, one needs to know both the dose equivalent rate constants for soft tissue and barrier transmission factors (TFs) for all radionuclides of interest. Dose equivalent rate constants are most commonly calculated using published air kerma or exposure rate constants, while transmission factors are most commonly calculated using published tenth-value layers (TVLs). Values can be calculated more accurately using the radionuclide's photon emission spectrum and the physical properties of lead, concrete, and/or tissue at these energies. These calculations may be non-trivial due to the polyenergetic nature of the radionuclides used in nuclear medicine. In this paper, the effects of dose equivalent rate constant and transmission factor on nuclear medicine dose and shielding calculations are investigated, and new values based on up-to-date nuclear data and thresholds specific to nuclear medicine are proposed. To facilitate practical use, transmission curves were fitted to the three-parameter Archer equation. Finally, the results of this work were applied to the design of a sample nuclear medicine facility and compared to doses calculated using common methods to investigate the effects of these values on dose estimates and shielding decisions. Dose equivalent rate constants generally agreed well with those derived from the literature with the exception of those from NCRP 124. Depending on the situation, Archer fit TFs could be significantly more accurate than TVL-based TFs. These results were reflected in the sample shielding problem, with unshielded dose estimates agreeing well, with the exception of those based on NCRP 124, and Archer fit TFs providing a more accurate alternative to TVL TFs and a simpler alternative to full spectral-based calculations. The data provided by this paper should assist in improving the accuracy and tractability of dose and shielding calculations for nuclear medicine facility design.

摘要

核医学设施设计的主要目标是使公众和工作人员的辐射剂量保持在合理可行尽量低(ALARA)。为了估计剂量和屏蔽要求,需要知道所有感兴趣的放射性核素的软组织剂量当量率常数和屏障传输因子(TFs)。剂量当量率常数最常用公布的空气比释动能或照射率常数计算,而传输因子最常用公布的十分之一值层(TVL)计算。可以使用放射性核素的光子发射光谱和这些能量下的铅、混凝土和/或组织的物理特性更准确地计算这些值。由于核医学中使用的放射性核素的多能性质,这些计算可能很复杂。在本文中,研究了剂量当量率常数和传输因子对核医学剂量和屏蔽计算的影响,并提出了基于最新核数据和核医学特定阈值的新值。为了便于实际使用,传输曲线拟合到三参数 Archer 方程。最后,将这项工作的结果应用于一个示例核医学设施的设计,并与使用常见方法计算的剂量进行比较,以调查这些值对剂量估算和屏蔽决策的影响。剂量当量率常数除了 NCRP 124 外,通常与文献中推导的值吻合较好。根据具体情况,Archer 拟合 TF 可以比基于 TVL 的 TF 更准确。这些结果反映在示例屏蔽问题中,除了基于 NCRP 124 的结果外,无屏蔽剂量估算值吻合较好,Archer 拟合 TF 为 TVL TF 提供了更准确的替代方案,为全谱计算提供了更简单的替代方案。本文提供的数据应有助于提高核医学设施设计中剂量和屏蔽计算的准确性和可处理性。

相似文献

1
Dose equivalent rate constants and barrier transmission data for nuclear medicine facility dose calculations and shielding design.核医学设施剂量计算和屏蔽设计的剂量当量率常数和势垒透射数据。
Health Phys. 2014 Jul;107(1):60-72. doi: 10.1097/HP.0000000000000051.
2
Brachytherapy structural shielding calculations using Monte Carlo generated, monoenergetic data.使用蒙特卡罗生成的单能数据进行近距离放射治疗结构屏蔽计算。
Med Phys. 2014 Apr;41(4):043901. doi: 10.1118/1.4868456.
3
Radiation transmission data for radionuclides and materials relevant to brachytherapy facility shielding.与近距离放射治疗设施屏蔽相关的放射性核素和材料的辐射传输数据。
Med Phys. 2008 Nov;35(11):4898-906. doi: 10.1118/1.2986153.
4
Methodology for worker neutron exposure evaluation in the PDCF facility design.PDCF设施设计中工人中子照射评估的方法学。
Radiat Prot Dosimetry. 2004;110(1-4):725-9. doi: 10.1093/rpd/nch174.
5
Monte Carlo simulations of ceiling scatter in nuclear medicine: Tc, I and F.核医学中天花板散射的蒙特卡罗模拟:锝、碘和氟。
Med Phys. 2017 Mar;44(3):1113-1119. doi: 10.1002/mp.12113.
6
Comparison of the CT scatter fractions provided in NCRP Report No. 147 to scanner-specific scatter fractions and the consequences for calculated barrier thickness.将NCRP第147号报告中提供的CT散射分数与特定扫描仪的散射分数进行比较以及对计算出的屏蔽厚度的影响。
Health Phys. 2007 Aug;93(2):165-70. doi: 10.1097/01.HP.0000263402.32520.18.
7
Comparison of four methods used in determination of secondary shielding requirements for a teletherapy facility: a case study of 137Cs room in Tanzania.用于远距离治疗设施二次屏蔽要求测定的四种方法比较:以坦桑尼亚的137Cs治疗室为例
Appl Radiat Isot. 2004 Dec;61(6):1295-302. doi: 10.1016/j.apradiso.2003.12.012.
8
Genotoxic and reprotoxic effects of tritium and external gamma irradiation on aquatic animals.氚和外照射γ 射线对水生动物的遗传毒性和生殖毒性效应。
Rev Environ Contam Toxicol. 2012;220:67-103. doi: 10.1007/978-1-4614-3414-6_3.
9
Operational radiation safety for PET-CT, SPECT-CT, and cyclotron facilities.正电子发射断层显像-计算机断层扫描(PET-CT)、单光子发射计算机断层扫描-计算机断层扫描(SPECT-CT)和回旋加速器设施的辐射安全操作
Health Phys. 2008 Nov;95(5):554-70. doi: 10.1097/01.HP.0000327651.15794.f7.
10
Analytical shielding calculations for a proton therapy facility.质子治疗设施的分析屏蔽计算。
Radiat Prot Dosimetry. 2008;131(2):167-79. doi: 10.1093/rpd/ncn136. Epub 2008 May 16.