Weiss W, Larsson C-M, McKenney C, Minon J-P, Mobbs S, Schneider T, Umeki H, Hilden W, Pescatore C, Vesterlind M
Ann ICRP. 2013 Jun;42(3):1-57. doi: 10.1016/j.icrp.2013.01.001.
This report updates and consolidates previous recommendations of the International Commission on Radiological Protection (ICRP) related to solid waste disposal (ICRP, 1985, 1997b, 1998). The recommendations given apply specifically to geological disposal of long-lived solid radioactive waste. The report explains how the ICRP system of radiological protection described in Publication 103 (ICRP, 2007) can be applied in the context of the geological disposal of long-lived solid radioactive waste. Although the report is written as a standalone document, previous ICRP recommendations not dealt with in depth in the report are still valid. The 2007 ICRP system of radiological protection evolves from the previous process-based protection approach relying on the distinction between practices and interventions by moving to an approach based on the distinction between three types of exposure situation: planned, emergency and existing. The Recommendations maintains the Commission's three fundamental principles of radiological protection namely: justification, optimisation of protection and the application of dose limits. They also maintain the current individual dose limits for effective dose and equivalent dose from all regulated sources in planned exposure situations. They re-enforce the principle of optimisation of radiological protection, which applies in a similar way to all exposure situations, subject to restrictions on individual doses: constraints for planned exposure situations, and reference levels for emergency and existing exposure situations. The Recommendations also include an approach for developing a framework to demonstrate radiological protection of the environment. This report describes the different stages in the life time of a geological disposal facility, and addresses the application of relevant radiological protection principles for each stage depending on the various exposure situations that can be encountered. In particular, the crucial factor that influences the application of the protection system over the different phases in the life time of a disposal facility is the level of oversight or 'watchful care' that is present. The level of oversight affects the capability to control the source, i.e. the waste and the repository, and to avoid or reduce potential exposures. Three main time frames are considered: time of direct oversight, when the disposal facility is being implemented and is under active supervision; time of indirect oversight, when the disposal facility is sealed and oversight is being exercised by regulators or special administrative bodies or society at large to provide additional assurance on behalf of society; and time of no oversight, when oversight is no longer exercised in case memory of the disposal facility is lost.
本报告更新并整合了国际放射防护委员会（ICRP）先前有关固体废物处置的建议（ICRP，1985年、1997b、1998年）。所给出的建议具体适用于长寿命固体放射性废物的地质处置。本报告解释了第103号出版物（ICRP，2007年）中描述的ICRP放射防护体系如何应用于长寿命固体放射性废物的地质处置背景。尽管本报告作为一份独立文件编写，但报告中未深入涉及的ICRP先前建议仍然有效。2007年ICRP放射防护体系是从先前基于过程的防护方法发展而来，先前的方法依赖于实践与干预之间的区分，现在转变为基于以下三种照射情况之间区分的方法：计划照射情况、应急照射情况和现存照射情况。本建议书保持了委员会放射防护的三项基本原则，即：正当性、防护最优化和剂量限值的应用。它们还维持了计划照射情况下来自所有受监管源的有效剂量和当量剂量的现行个人剂量限值。它们强化了放射防护最优化原则，该原则以类似方式适用于所有照射情况，但需对个人剂量加以限制：计划照射情况下的约束值以及应急和现存照射情况下的参考水平。本建议书还包括一种用于制定一个框架以证明对环境的放射防护的方法。本报告描述了地质处置设施寿命期内的不同阶段，并根据可能遇到的各种照射情况阐述了每个阶段相关放射防护原则的应用。特别是，在处置设施寿命期的不同阶段影响防护体系应用的关键因素是存在的监管或“密切关注”水平。监管水平影响控制源（即废物和处置库）以及避免或减少潜在照射的能力。考虑了三个主要时间框架：直接监管期，即处置设施正在实施且受到积极监督的时期；间接监管期，即处置设施封闭后由监管机构、特殊管理机构或整个社会进行监管以为社会提供额外保证的时期；无监管期，即万一处置设施的记忆丧失而不再进行监管的时期。
