1.1 本规程涵盖高强度辐照程序，旨在支持使用基于加速器的中子源进行材料损伤等效研究。讨论的重点是两种类型的源，即氘-氚T（d，n）相互作用产生的近单能14MeV中子，以及阻止厚铍或锂靶中氘束的广谱中子。然而，大多数建议也适用于其他类型的加速器源，包括散裂中子源 ( 1. ) . 2. 由于开发了用于中子散射的高功率、高通量率源，人们对散裂源的兴趣有所增加 ( 2. 4. ) 以及它们在裂变反应堆废料嬗变中的拟议用途 ( 5. ) . 1.2 使用这种中子源进行的许多实验旨在提供另一中子光谱中的辐射模拟，例如来自DT聚变反应的辐射。 这里使用的模拟一词在广义上是指对相关中子辐照环境的近似。一致性的程度可以从差到几乎准确不等。通常，这些实验的目的是建立辐射或材料参数与材料响应之间的基本关系。对此类实验数据的外推需要考虑中子光谱的差异。 1.3 要考虑的程序包括表征加速器束和目标、辐照样品、中子注量率（不推荐使用的术语“通量”的推荐术语）和光谱的方法，以及记录和报告辐照数据的程序。 1.4 其他实验问题，如温度控制，不包括在内。 1.5 以国际单位制表示的数值应视为标准。本标准不包括其他计量单位。 1.6 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制定适当的安全、健康和环境实践，并确定监管限制的适用性。 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。

1.1 This practice covers procedures for high-intensity irradiations designed to support material damage equivalence studies using accelerator-based neutron sources. The discussion focuses on two types of sources, namely nearly monoenergetic 14-MeV neutrons from the deuterium-tritium T(d,n) interaction, and broad spectrum neutrons from stopping deuterium beams in thick beryllium or lithium targets. However, most of the recommendations also apply to other types of accelerator-based sources, including spallation neutron sources ( 1 ) . 2 Interest in spallation sources has increased due to the development of high-power, high-fluence rate sources for neutron scattering ( 2- 4 ) and their proposed use for transmutation of fission reactor waste ( 5 ) . 1.2 Many of the experiments conducted using such neutron sources are intended to provide a simulation of irradiation in another neutron spectrum, for example, that from a DT fusion reaction. The word simulation is used here in a broad sense to imply an approximation of the relevant neutron irradiation environment. The degree of conformity can range from poor to nearly exact. In general, the intent of these experiments is to establish the fundamental relationships between irradiation or material parameters and the material response. The extrapolation of data from such experiments requires that the differences in neutron spectra be considered. 1.3 The procedures to be considered include methods for characterizing the accelerator beam and target, the irradiated sample, and the neutron fluence rate (recommended terminology for the deprecated term “flux”) and spectrum, as well as procedures for recording and reporting irradiation data. 1.4 Other experimental problems, such as temperature control, are not included. 1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard. 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.