1.1 本实践涵盖了中总结的方法 附件A1 用于分析和解释试验反应堆的物理剂量测定结果。 1.2 本实践依赖并联系了几个支持ASTM标准实践、指南和方法的应用。 1.3 讨论的支持主题领域包括反应堆物理计算、剂量计选择和分析、暴露单元和中子光谱调整方法。 1.4 本规程旨在开发和应用从试验反应堆辐照实验中获得的物理剂量学冶金数据，以支持轻水堆核电站的运行、许可和监管。它具体解决了该问题的物理剂量学方面。与测试和动力反应堆物理的分析、解释和应用相关的程序- 剂量学冶金结果在实践中得到解决 E185 , E853 和 E1035 ，导向装置 E900 , 2005年 , 2006年 和试验方法 E646 . 另请参见 E706 . 1.5 本标准并非旨在解决与其使用相关的所有安全问题（如有）。本标准的用户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。 1.6 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《关于制定国际标准、指南和建议的原则的决定》中确立的国际公认标准化原则制定的。 ====意义和用途====== 3.1 暴露于中子辐射会改变钢和其他金属的机械性能。 假设这些性质变化是化学成分、冶金条件、温度、注量（也可能是注量率）和中子谱的函数。这些变量的影响尚未完全理解。属性变化与中子辐射之间的函数依赖性以损伤暴露参数的形式总结，损伤暴露参数是中子注量谱上的加权积分。 3.2 评估中子辐射对压力容器钢的影响和确定安全限值需要了解辐射暴露参数预测中的不确定性（例如dpa（实践 E693 )，中子注量大于1.0 MeV，中子注量大于0.1 MeV，热中子注量等）。本规程描述了用于确定试验反应堆实验的这些暴露参数（以及相关不确定性）的推荐程序和数据。 3.3 核工业的大部分信息来自于试验反应堆实验的数据库。因此，从试验反应堆获得可靠的数据库以评估轻水反应堆核电站的安全问题至关重要。

1.1 This practice covers the methodology summarized in Annex A1 to be used in the analysis and interpretation of physics-dosimetry results from test reactors. 1.2 This practice relies on, and ties together, the application of several supporting ASTM standard practices, guides, and methods. 1.3 Support subject areas that are discussed include reactor physics calculations, dosimeter selection and analysis, exposure units, and neutron spectrum adjustment methods. 1.4 This practice is directed towards the development and application of physics-dosimetry-metallurgical data obtained from test reactor irradiation experiments that are performed in support of the operation, licensing, and regulation of LWR nuclear power plants. It specifically addresses the physics-dosimetry aspects of the problem. Procedures related to the analysis, interpretation, and application of both test and power reactor physics-dosimetry-metallurgy results are addressed in Practices E185 , E853 , and E1035 , Guides E900 , E2005 , E2006 and Test Method E646 . See also E706 . 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 The mechanical properties of steels and other metals are altered by exposure to neutron radiation. These property changes are assumed to be a function of chemical composition, metallurgical condition, temperature, fluence (perhaps also fluence rate), and neutron spectrum. The influence of these variables is not completely understood. The functional dependency between property changes and neutron radiation is summarized in the form of damage exposure parameters that are weighted integrals over the neutron fluence spectrum. 3.2 The evaluation of neutron radiation effects on pressure vessel steels and the determination of safety limits requires the knowledge of uncertainties in the prediction of radiation exposure parameters (for example, dpa (Practice E693 ), neutron fluence greater than 1.0 MeV, neutron fluence greater than 0.1 MeV, thermal neutron fluence, etc.). This practice describes recommended procedures and data for determining these exposure parameters (and the associated uncertainties) for test reactor experiments. 3.3 The nuclear industry draws much of its information from databases that come from test reactor experiments. Therefore, it is essential that reliable databases are obtained from test reactors to assess safety issues in Light Water Reactor (LWR) nuclear power plants.