1.1 本实施规程概述了独立干燥储存γ辐照器应遵循的剂量测定程序。对于用于常规加工的辐照器，给出了程序以确保加工产品将在规定限度内接收吸收剂量。 1.2 本规范涵盖了使用干式储存伽马辐照器（即独立干式储存）时的剂量测定 137 Cs或 60 一氧化碳辐照器（屏蔽独立式辐照器）。它不包括水下水池源、全景伽马源，也不包括独立的轫致辐射X射线装置。 1.3 本实施例所涵盖的用于使用干燥储存的独立伽马辐照器的吸收剂量范围通常为1至10 5 Gy，取决于应用。吸收剂量率范围通常为10 –2 至10 3 Gy/min。 1.4 对于为特定应用提供的辐照器，特定的ISO或ASTM实践和指南提供了该应用的剂量测定程序。有关血液辐照剂量测定的具体程序，请参见ASTM实践 51939 关于食品和农产品辐射研究中剂量测定的具体程序，见ASTM实践 51900 关于辐射硬度测试的具体程序，见ASTM实践 E1249 关于无菌释放程序中昆虫辐照剂量测定的具体程序，见ASTM指南 51940 在ASTM涵盖的情况下 51939 , 51900 , 51940 ，或 E1249 ，以这些标准为准。 1.5 本文件是一套标准之一，为在辐射处理中正确实施和利用剂量测定提供了建议。它旨在与ASTM一起阅读 E2628 ，“辐射处理中剂量测定的实践”。 1.6 本标准并不旨在解决与其使用相关的所有安全性问题（如果有）。本标准的使用者有责任在使用前建立适当的安全、健康和环境实践并确定法规限制的适用性。 1.7 本国际标准是根据世界贸易组织技术性贸易壁垒委员会发布的《关于制定国际标准、指南和建议的原则的决定》中确立的国际公认的标准化原则制定的。 ======意义和用途====== 4.1 自-包含的辐照器应确保在使用相同辐照参数时获得可重复的吸收剂量。进行剂量测定以确定辐射参数和吸收剂量之间的关系。 4.1.1 对于大多数应用，吸收剂量表示为对水的吸收剂量（参见ASTM实践 51261 ).对于水的吸收剂量到其他材料（例如硅）的吸收剂量的转换，参见ASTM实践附录A1 51261 . 4.2 独立式干贮伽马辐照器包含适当屏蔽的放射源，即 137 Cs或 60 Co，发射电离电磁辐射（伽马辐射）。这些辐照器具有封闭的、可接近的辐照器样品室，该辐照器样品室与样品定位系统连接，例如辐照器抽屉、转子或辐照器转盘，作为辐照装置的一部分。4.3 独立的干式储存伽马辐照器可用于许多辐射处理应用，包括剂量计的校准辐照；剂量计影响量的研究；辐射效应研究，以及用于工艺相容性研究的材料或生物样品的辐照；微生物、植物或体外样品的批量辐照；照射小动物；电子元件和其他材料的辐射“硬度”测试；以及样品容器的批量辐射处理。 附注1: 自包含的干式储存γ辐照器包含密封辐射源，或安全地保持在由固体材料构成的干燥容器中的密封辐射源阵列。密封的辐射源在任何时候都被屏蔽，并且由于辐照器的设计配置，人在物理上不可能接近经受辐照的腔室（参见ANSI/HPS N43。7). 附注2: 对于参考标准剂量测定，吸收剂量和吸收剂量率可以用水或具有与被照射的样品或剂量计的辐射吸收特性相似的辐射吸收特性的其他材料来表示。在一些情况下，参考标准剂量测定可以使用电离室进行，并且可以根据暴露量（C kg –1 ），或对空气、水或组织的吸收剂量（Gy）。根据暴露进行的测量适用于空气中的电离，并且应注意将该测量应用于被照射的样品。

1.1 This practice outlines dosimetric procedures to be followed with self-contained dry-storage gamma irradiators. For irradiators used for routine processing, procedures are given to ensure that product processed will receive absorbed doses within prescribed limits. 1.2 This practice covers dosimetry in the use of dry-storage gamma irradiators, namely self-contained dry-storage 137 Cs or 60 Co irradiators (shielded freestanding irradiators). It does not cover underwater pool sources, panoramic gamma sources, nor does it cover self-contained bremsstrahlung X-ray units. 1.3 The absorbed-dose range for the use of the dry-storage self-contained gamma irradiators covered by this practice is typically 1 to 10 5 Gy, depending on the application. The absorbed-dose rate range typically is from 10 –2 to 10 3 Gy/min. 1.4 For irradiators supplied for specific applications, specific ISO or ASTM practices and guides provide dosimetric procedures for the application. For procedures specific to dosimetry in blood irradiation, see ASTM Practice 51939 . For procedures specific to dosimetry in radiation research on food and agricultural products, see ASTM Practice 51900 . For procedures specific to radiation hardness testing, see ASTM Practice E1249 . For procedures specific to the dosimetry in the irradiation of insects for sterile release programs, see ASTM Guide 51940 . In those cases covered by ASTM 51939 , 51900 , 51940 , or E1249 , those standards take precedence. 1.5 This document is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ASTM E2628 , “Practice for Dosimetry in Radiation Processing.” 1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use. 1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee. ====== Significance And Use ====== 4.1 The design and operation of a self-contained irradiator should ensure that reproducible absorbed doses are obtained when the same irradiation parameters are used. Dosimetry is performed to determine the relationship between the irradiation parameters and the absorbed dose. 4.1.1 For most applications, the absorbed dose is expressed as absorbed dose to water (see ASTM Practice 51261 ). For conversion of absorbed dose to water to that to other materials, for example, silicon, see Annex A1 of ASTM Practice 51261 . 4.2 Self-contained dry-storage gamma irradiators contain properly shielded radioactive sources, namely 137 Cs or 60 Co, that emit ionizing electromagnetic radiation (gamma radiation). These irradiators have an enclosed, accessible irradiator sample chamber connected with a sample positioning system, for example, irradiator drawer, rotor, or irradiator turntable, as part of the irradiation device. 4.3 Self-contained dry-storage gamma irradiators can be used for many radiation processing applications, including the calibration irradiation of dosimeters; studies of dosimeter influence quantities; radiation effects studies, and irradiation of materials or biological samples for process compatibility studies; batch irradiations of microbiological, botanical, or in-vitro samples; irradiation of small animals; radiation “hardness” testing of electronics components and other materials; and batch radiation processing of containers of samples. Note 1: Self-contained dry-storage gamma irradiators contain a sealed radiation source, or an array of sealed radiation sources securely held in a dry container constructed of solid materials. The sealed radiation sources are shielded at all times, and human access to the chamber undergoing irradiation is not physically possible due to the irradiator’s design configuration (see ANSI/HPS N43.7). Note 2: For reference–standard dosimetry, the absorbed dose and absorbed-dose rate can be expressed in water or other material which has similar radiation absorption properties to that of the samples or dosimeters being irradiated. In some cases, the reference-standard dosimetry may be performed using ionization chambers, and may be calibrated in terms of exposure (C kg –1 ), or absorbed dose to air, water or tissue (Gy). Measurements performed in terms of exposure apply to ionization in air, and care should be taken to apply that measurement to the sample being irradiated.