1.1 本标准指南定义了制定核设施退役混凝土处置策略的过程。它概述了评估放射性污染混凝土处置方案的10步方法。其中一个步骤是完成对非辐射工作人员（公众）的成本和剂量的详细分析；执行该分析的方法和支持数据详见附录。所得数据可用于平衡剂量和成本，并选择最佳处置方案。这些数据建立了适用于释放混凝土的技术基础，可通过几种方式使用:( 1. )为了证明发布符合现有发布标准( 2. )根据具体情况，确定要求释放混凝土的依据( 3. )在没有发布标准的情况下，为制定发布标准奠定基础。 1.2 本标准指南基于“美国混凝土协会制定混凝土授权释放限值的协议”。 S、 能源部现场，”( 1. ) 2. 从中获取分析方法和支持数据。 1.3 指导 E1760 提供了释放含有残余放射性物质的一般过程。此外，指南 E1278 提供分析放射性路径的一般过程。本标准指南旨在与指南一起使用 E1760 和 E1278 ，并提供了更详细的混凝土释放方法。 1.4 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====== 4.1 本标准指南适用于仍处于规定几何形状和已知记录历史的混凝土。 4.2 它不适用于已经橡胶化的混凝土，因为在橡胶化混凝土后，很难测量辐射水平，也不容易去除表面污染以降低辐射水平。 4.3 本标准指南适用于表面或体积受污染的混凝土，其中污染深度可以根据混凝土的历史进行测量或估计。 4.4 本标准指南不适用于混凝土中的钢筋。尽管大多数混凝土包含钢筋，但通常在处理混凝土之前将其移除。此外，钢筋可以被激活，并包含在废金属再利用程序中。 4.5 本标准指南附录中提供了支持计算的一般单位剂量和单位成本数据。然而，如果可以获得现场特定数据，则应使用该数据，而不是此处提供的一般信息。 4.6 本标准指南有助于确定混凝土处置期间公众和处置区未来居民的估计剂量。它不包括已经参与辐射控制计划的辐射工作人员的剂量。假设辐射工作人员的剂量已经通过辐射控制计划跟踪并保持在可接受水平内。 可以将辐射工作人员的成本和剂量加进去，以找到每个选项的总体成本和剂量。

1.1 This standard guide defines the process for developing a strategy for dispositioning concrete from nuclear facility decommissioning. It outlines a 10-step method to evaluate disposal options for radioactively contaminated concrete. One of the steps is to complete a detailed analysis of the cost and dose to nonradiation workers (the public); the methodology and supporting data to perform this analysis are detailed in the appendices. The resulting data can be used to balance dose and cost and select the best disposal option. These data, which establish a technical basis to apply to release the concrete, can be used in several ways: ( 1 ) to show that the release meets existing release criteria, ( 2 ) to establish a basis to request release of the concrete on a case-by-case basis, ( 3 ) to develop a basis for establishing release criteria where none exists. 1.2 This standard guide is based on the “Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites,” ( 1 ) 2 from which the analysis methodology and supporting data are taken. 1.3 Guide E1760 provides a general process for release of materials containing residual amounts of radioactivity. In addition, Guide E1278 provides a general process for analyzing radioactive pathways. This standard guide is intended for use in conjunction with Guides E1760 and E1278 , and provides a more detailed approach for the release of concrete. 1.4 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 This standard guide applies to concrete that is still in place with a defined geometry and known, documented history. 4.2 It is not intended for use on concrete that has already been rubbelized where it is difficult to measure the radiation levels and not easy to remove surface contamination to reduce radiation levels after concrete has been rubbelized. 4.3 This standard guide applies to surface or volumetrically contaminated concrete, where the depth of contamination can be measured or estimated based on the history of the concrete. 4.4 This standard guide does not apply to the reinforcement bar (rebar) found in concrete. Although most concrete contains rebar, it is generally removed before the concrete is dispositioned. In addition, rebar may be activated, and is covered under procedures for reuse of scrap metal. 4.5 General unit-dose and unit-cost data to support the calculations is provided in the appendices of this standard guide. However, if site-specific data is available, it should be used instead of the general information provided here. 4.6 This standard guide helps determine estimated doses to the public during disposal of concrete and to future residents of disposal areas. It does not include dose to radiation workers already involved in a radiation control program. It is assumed that the dose to radiation workers is already tracked and kept within acceptable levels through a radiation control program. The cost and dose to radiation workers could be added in to find an overall cost and dose for each option.