本标准包含计算核电站辐射屏蔽所需混凝土厚度所需的方法和数据。在可能的情况下，就辐射衰减计算、屏蔽设计和文件标准提出具体建议。它为负责固定核电站屏蔽设计的建筑工程师、公共设施和反应堆供应商提供指导。它不考虑与核电站相关的其他辐射源。屏蔽设计的经济方面也不包括在内。混凝土是一种材料混合物，其确切比例因应用而异。本标准包括对混凝土性质的讨论，强调了对屏蔽设计人员重要的材料的可变方面。该文件讨论了分析方法和适用于每种方法的屏蔽输入数据。 给出了分析方法的应用，包括散装运输、辐射加热、流动和反射问题。

This standard contains methods and data needed to calculate the concrete thickness required for radiation shielding in nuclear power plants. Where possible, specific recommendations regarding radiation attenuation calculations, shielding design, and standards of documentation are made. It provides guidance to architect-engineers, utilities, and reactor vendors who are responsible for the shielding design of stationary nuclear plants. It does not consider sources of radiation other than those associated with nuclear power plants. It also excludes considerations of economic aspects of shielding design. Concrete is a mixture of materials, the exact proportions of which will differ from application to application. This standard includes a discussion of the nature of concrete, emphasizing those variable aspects of the material that are important to the shield designer. The document discusses methods of analysis and the shielding input data appropriate to each method. Applications of the analytical methods are given, including bulk transport, radiation heating, streaming, and reflection problems.