ISO 6980-1:2023 核能 β粒子参考辐射 第1部分：产生方法
标准编号：ISO 6980-1:2023
中文名称：核能 β粒子参考辐射 第1部分：产生方法
英文名称：Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production
发布日期：2023-11
标准范围
本文件规定了由放射源产生的参考β辐射场的要求，这些参考β辐射场用于校准个人和区域剂量计以及剂量率计，用于确定量Hp（0，07）、H’（0，07；Ω）、Hp（3）和H’（3；Ω），以及确定它们作为β粒子能量和入射角函数的响应。β剂量测定中的基本量是组织等效平板体模中的吸收剂量率。该文件给出了用于产生参考β辐射场的放射性核素的特性，给出了合适的源结构的示例，并描述了在0.07？深度处测量残余最大β粒子能量和剂量当量率的方法？国际辐射单位和测量委员会（ICRU）领域的毫米。所涉及的能量范围在0.22？MeV和3,6？MeV最大β能量对应于0.07？小姐是1.2？MeV平均β能量和剂量当量率在大约？10？μ Sv·h-1至至少10？Sv·h-1..此外，对于一些源，给出了作为入射角函数的剂量当量率的变化。然而，正如ICRU所指出的？56[5]中，用于区域监测的环境剂量当量H*（10）和用于个体监测的个人剂量当量Hp（10）对于任何β辐射都不是合适的量，即使是穿透10？毫米的组织（Emax？>？2？MeV）。本文件适用于两个系列的参考β辐射场，从中可以选择确定仪器特性（校准和响应的能量和角度依赖性）所需的辐射。系列？1参考辐射场是由与波束平坦滤光器一起使用的放射源产生的，波束平坦滤光器被设计成在指定距离的大面积上给出均匀的剂量当量率。建议的106Ru/106Rh、90Sr/90Y、85Kr、204Tl和147Pm源产生的最大剂量当量率约为？200？mSv·h-1。系列？2在不使用射束平坦滤波器的情况下产生参考辐射场，这允许使用大面积平面源和源到校准平面距离的范围。靠近源，只产生相对较小的均匀剂量率区域，但该系列具有将能量和剂量率范围扩展到系列之外的优点？1.该系列还包括使用聚甲基丙烯酸甲酯（PMMA）吸收剂来降低最大β粒子能量的辐射场。使用的放射性核素是系列的放射性核素？1;这些来源产生的剂量当量率高达？10？Sv·H-1。
This document specifies the requirements for reference beta radiation fields produced by radioactive sources to be used for the calibration of personal and area dosemeters and dose-rate meters to be used for the determination of the quantities Hp(0,07), H'(0,07;Ω), Hp(3) and H'(3;Ω), and for the determination of their response as a function of beta particle energy and angle of incidence. The basic quantity in beta dosimetry is the absorbed-dose rate in a tissue-equivalent slab phantom. This document gives the characteristics of radionuclides that have been used to produce reference beta radiation fields, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta particle energy and the dose equivalent rate at a depth of 0,07 mm in the International Commission on Radiation Units and Measurements (ICRU) sphere. The energy range involved lies between 0,22 MeV and 3,6 MeV maximum beta energy corresponding to 0,07 MeV to 1,2 MeV mean beta energy and the dose equivalent rates are in the range from about 10 μSv·h-1 to at least 10 Sv·h-1.. In addition, for some sources, variations of the dose equivalent rate as a function of the angle of incidence are given. However, as noted in ICRU 56[5], the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is applicable to two series of reference beta radiation fields, from which the radiation necessary for determining the characteristics (calibration and energy and angular dependence of response) of an instrument can be selected.
Series 1 reference radiation fields are produced by radioactive sources used with beam-flattening filters designed to give uniform dose equivalent rates over a large area at a specified distance. The proposed sources of 106Ru/106Rh, 90Sr/90Y, 85Kr, 204Tl and 147Pm produce maximum dose equivalent rates of approximately 200 mSv·h–1.
Series 2 reference radiation fields are produced without the use of beam-flattening filters, which allows large area planar sources and a range of source-to-calibration plane distances to be used. Close to the sources, only relatively small areas of uniform dose rate are produced, but this series has the advantage of extending the energy and dose rate ranges beyond those of series 1. The series also include radiation fields using polymethylmethacrylate (PMMA) absorbers to reduce the maximum beta particle energy. The radionuclides used are those of series 1; these sources produce dose equivalent rates of up to 10 Sv·h–1.
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