1.1 本指南涵盖了用于电子半导体器件辐射硬度测试的中子谱调整技术中中子活化探测器材料的选择和使用。描述了在许多辐射硬度测试设施中使用的传感器，并在表脚注中提供了关于每个反应的适当性的评论，这些评论通过其横截面精度、作为传感器的易用性以及过去的成功应用来判断。本指南还讨论了在选择传感器厚度、传感器盖和传感器位置时需要考虑的注量均匀性、中子自屏蔽和注量下降校正。 这些考虑因素与确定TRIGA和Godiva型反应堆等组件以及加利福尼亚辐照器的中子光谱有关。本指南还可适用于高达20MeV的其他宽能量分布源。 注1: 有关本指南中使用的术语的定义，请参阅术语 第170页 . 1.2 本指南还包括测量活化箔和其他传感器的伽马射线或β射线发射率，以及计算这些箔的绝对比活度。主要的测量技术是高分辨率伽马射线光谱法。这些活动用于确定能量- 中子源的注量谱。请参阅指南 E721型 . 1.3 测量和分析详情如下: 1.3.1 测量传感器活动所涉及的校正包括伽马射线探测器校准中有限传感器尺寸和厚度的校正、脉冲高度分析仪死区时间和脉冲堆积损失的校正以及背景放射性的校正。 1.3.2 本指南和测试方法中考虑了使用次级标准伽马射线发射源的探测器校准的主要方法 1981年 此外，指南中讨论了在基准中子场的已知光谱中激活传感器的替代方法 2018年 . 1.3.3 提出了一种数据分析方法，该方法考虑了以下因素:探测器效率；背景减影；辐照、等待和计数时间；裂变产额和伽马射线分支比；以及传感器中伽马射线和中子的自吸收。 1.4 以国际单位制表示的值应视为标准值。本标准不包括其他测量单位。 1.5 本标准并不旨在解决与其使用相关的所有安全问题（如有）。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，并确定监管限制的适用性。 1.6 本国际标准是根据世界贸易组织技术性贸易壁垒（TBT）委员会发布的《国际标准、指南和建议制定原则决定》中确立的国际公认标准化原则制定的。 =====意义和用途====== 3.1 由于中子活化测量中使用的材料种类繁多，因此本指南的目的是提高此处感兴趣的特定领域的均匀性:主要在关键组装反应堆环境中对电子器件进行硬度测试。 注2: 所讨论的一些技术对14- MeV剂量测定。参见测试方法 第496页 适用于14MeV中子效应测试的活化探测器材料。 注3: 本指南中推荐的材料适用于 252 Cf或其他弱源效应测试，前提是通量足以产生可计数的活动。 3.2 本指南分为两个重叠的主题:用于传感器选择的标准和用于确保正确确定中子光谱测定活动的程序。参见术语 第170页 和测试方法 1981年 指南中讨论了利用活化传感器数据测定中子光谱 E721型 和 E944年 .

1.1 This guide covers the selection and use of neutron-activation detector materials to be employed in neutron spectra adjustment techniques used for radiation-hardness testing of electronic semiconductor devices. Sensors are described that have been used at many radiation hardness-testing facilities, and comments are offered in table footnotes concerning the appropriateness of each reaction as judged by its cross-section accuracy, ease of use as a sensor, and by past successful application. This guide also discusses the fluence-uniformity, neutron self-shielding, and fluence-depression corrections that need to be considered in choosing the sensor thickness, the sensor covers, and the sensor locations. These considerations are relevant for the determination of neutron spectra from assemblies such as TRIGA- and Godiva-type reactors and from Californium irradiators. This guide may also be applicable to other broad energy distribution sources up to 20 MeV. Note 1: For definitions on terminology used in this guide, see Terminology E170 . 1.2 This guide also covers the measurement of the gamma-ray or beta-ray emission rates from the activation foils and other sensors as well as the calculation of the absolute specific activities of these foils. The principal measurement technique is high-resolution gamma-ray spectrometry. The activities are used in the determination of the energy-fluence spectrum of the neutron source. See Guide E721 . 1.3 Details of measurement and analysis are covered as follows: 1.3.1 Corrections involved in measuring the sensor activities include those for finite sensor size and thickness in the calibration of the gamma-ray detector, for pulse-height analyzer deadtime and pulse-pileup losses, and for background radioactivity. 1.3.2 The primary method for detector calibration that uses secondary standard gamma-ray emitting sources is considered in this guide and in Test Methods E181 . In addition, an alternative method in which the sensors are activated in the known spectrum of a benchmark neutron field is discussed in Guide E1018 . 1.3.3 A data analysis method is presented which accounts for the following: detector efficiency; background subtraction; irradiation, waiting, and counting times; fission yields and gamma-ray branching ratios; and self-absorption of gamma rays and neutrons in the sensors. 1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 1.5 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. 1.6 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 ====== 3.1 Because of the wide variety of materials being used in neutron-activation measurements, this guide is presented with the objective of bringing improved uniformity to the specific field of interest here: hardness testing of electronics primarily in critical assembly reactor environments. Note 2: Some of the techniques discussed are useful for 14-MeV dosimetry. See Test Method E496 for activation detector materials suitable for 14-MeV neutron effects testing. Note 3: The materials recommended in this guide are suitable for 252 Cf or other weak source effects testing provided the fluence is sufficient to generate countable activities. 3.2 This guide is organized into two overlapping subjects: the criteria used for sensor selection, and the procedures used to ensure the proper determination of activities for determination of neutron spectra. See Terminology E170 and Test Methods E181 . Determination of neutron spectra with activation sensor data is discussed in Guides E721 and E944 .