Near Surface Disposal of Radioactive Waste: Safety Requirements (Safety Standards Series No WS-R-1) and Safety Assessment for Near Surface Disposal of Radioactive Waste: Safety Guide (Safety Standards Series No WS-G-1.1)
Near Surface Disposal of Radioactive Waste: Safety Requirements (Safety Standards Series No WS-R-1) and Safety Assessment for Near Surface Disposal of Radioactive Waste: Safety Guide (Safety Standards Series No WS-G-1.1)
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放射性废物近地表处置：安全要求（安全标准系列编号 WS-R-1）和放射性废物近地表处置安全评估：安全指南（安全标准系列编号 WS-G-1.1）
DOI：
10.1088/0952-4746/22/2/707
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发表时间：
2002
期刊：
影响因子：
--
通讯作者：
D. Bennett
中科院分区：
文献类型：
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作者：
D. Bennett
放射性废物的近地面处置：安全要求（安全标准系列号WS-R-1）原子能机构维也纳：国际原子能机构ISBN：92-0-101099-0《放射性废物近地面处置安全评估：安全指南》（安全标准系列号WS-G-1.1）原子能机构维也纳：国际原子能机构ISBN：92-0-101299-3这两份补充文件已作为原子能机构的放射性同位素安全方案的一部分印发。《安全要求》出版物规定了在近地表处置库处置放射性废物的基本安全要求。《安全指南》涉及放射性废物近地表处置的安全评估，并就如何满足WS-R-1规定的要求提出了建议。《安全规定》的范围涵盖各种处置库设计，从地面结构到几十米深的岩洞。这种处置库一般针对含有短寿命放射性核素和低浓度长寿命放射性核素的废物。该文件主要针对新设施，但也建议可将其用于审查现有和以前的处置库。该文件指出，运行阶段的辐射防护要求需要适当考虑到基本安全标准。对于关闭后，标准应根据剂量、风险或两者。对于判定为可能发生的处置库演变模式，剂量或风险预测不应超过1 mSv/y剂量限值的某个适当分数或其风险当量。对于不太可能发生的事件，建议监管机构决定是否应将结果与风险约束进行比较，或者是否应分解剂量和发生概率。在规定组织要求时，该文件确定了废物产生者、处置库运营者和监管者应发挥的作用及其相互作用。该文件接着阐述了废物接收、处置库选址、处置库的设计、建造、运行和关闭以及关闭后阶段的要求。该条规定，在实际可行的情况下，封闭式处置库的安全不应依赖于需要持续采取积极措施的机构控制。本《安全指南》侧重于关闭后的安全评估;正是处置库长期的行为将处置库评估与对其他类型废物管理设施进行的运营评估区分开来。该指南讨论了安全评估的各种用途，包括在早期阶段确定可行性、选址、确定废物接受标准、支持许可证申请和帮助设计环境监测方案。强调了迭代方法的重要性。该指南的主要部分阐述了处置库安全评估的基本方法。它讨论了数据收集方案和概念模型和数学模型的开发，包括特征、事件和过程的处理以及设想方案。敏感性分析和不确定性的重要方面，以及它们如何联系描述。最后，讨论了建立信任措施。模型验证，校准和验证的方法，以及天然类似物的潜在用途和同行评审的结果。这两份文件很好地介绍了近地表处置库的要求，并为安全评估提供了指南。它们应该同样有用，既可以作为对这一复杂领域的新手的介绍，也可以作为对那些有更多经验的人的参考。
Near Surface Disposal of Radioactive Waste: Safety Requirements (Safety Standards Series No WS-R-1) IAEA Vienna: International Atomic Energy Agency ISBN: 92-0-101099-0 Safety Assessment for Near Surface Disposal of Radioactive Waste: Safety Guide (Safety Standards Series No WS-G-1.1) IAEA Vienna: International Atomic Energy Agency ISBN: 92-0-101299-3 These two complementary documents have been issued as part of the IAEA's RADWASS programme. The Safety Requirements publication sets out basic safety requirements for the disposal of radioactive wastes in near surface repositories. The Safety Guide addresses the safety assessment for near surface disposal of radioactive waste and provides recommendations on how to meet the requirements set out in WS-R-1. The scope of the Safety Requirements covers a wide range of repository designs, from above-ground structures to rock caverns at a few tens of metres depth. Such repositories are generally targeted at wastes containing short-lived radionuclides and low concentrations of long-lived radionuclides. The document is primarily aimed at new facilities, although the document suggests that it can be used in the review of existing and former repositories. The document states that radiation protection requirements for the operational phase need to take due account of the Basic Safety Standards. For post-closure, criteria should be in terms of dose, risk or both. For modes of repository evolution judged to be likely, projections of dose or risks should not exceed some appropriate fraction of the 1 mSv/y dose limit, or its risk equivalent. For unlikely events, it is suggested that the regulatory body should decide whether the outcome should be compared with the risk constraint, or whether dose and probability of occurrence should be disaggregated. In setting out organisational requirements, the document identifies what should be the roles of the waste generator, the repository operator and regulators, together with their interfaces. The document goes on to address requirements for waste acceptance, and repository siting, design, construction, operation and closure of the repository and post-closure phase. It states that as far as practicable, the safety of a closed repository shall not rely on institutional controls that necessitate continuing active measures. This Safety Guide concentrates on post-closure safety assessments; it is the behaviour of the repository over long periods which distinguishes repository assessments from the operational assessments as carried out for other types of waste management facilities. The guide discusses the various uses of safety assessments, from establishing feasibility at an early stage, siting, establishing waste acceptance criteria, support licence applications and helping to design environmental monitoring programmes. The importance of an iterative approach is stressed. The main part of the guide sets out the basic approach to repository safety assessments. It discusses data collection programmes and the development of conceptual and mathematical models, including the handling of features, events and processes (FEPS) and scenarios. The important aspects of sensitivity analyses and uncertainty and how they link are described. Finally, confidence-building measures are discussed. Methods of model verification, calibration and validation are described, as well as the potential uses of natural analogues and the peer review of results. These two documents provide a good introduction to the requirements for near surface repositories and a guide to safety assessments. They should be equally useful as an introduction to those new to this complex area, and as a reference for those with more experience.