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Experiences from the project on Validity of Safety goals

机译:来自项目安全目标有效性的经验

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The outcome of a probabilistic safety assessment (PSA) for a nuclear power plant is a combination of qualitative and quantitative results. Quantitative results are typically presented as the Core Damage Frequency (CDF) and as the frequency of an unacceptable radioactive release. In order to judge the acceptability of PSA results, criteria for the interpretation of results and the assessment of their acceptability need to be defined. Safety goals are defined in different ways in different countries and also used differently. Many countries are presently developing them in connection to the transfer to risk-informed regulation of both operating nuclear power plants (NPP) and new designs. However, it is far from self-evident how probabilistic safety criteria should be defined and used. On one hand, experience indicates that safety goals are valuable tools for the interpretation of results from a probabilistic safety assessment (PSA), and they tend to enhance the realism of a risk assessment. On the other hand, strict use of probabilistic criteria is usually avoided. A major problem is the large number of different uncertainties in PSA model, which makes it difficult to demonstrate the compliance with a probabilistic criterion. Further, it has been seen that PSA results can change a lot over time due to scope extensions, revised operating experience data, method development, or increases of level of detail, mostly leading to an increase of the frequency of the calculated risk. This can cause a problem of consistency in the judgments. The first phase of the project (2006) provided a general description of the issue of probabilistic safety goals for nuclear power plants, of important concepts related to the definition and application of safety goals, and of experiences in Finland and Sweden. The second, third and fourth phases (2007-2009) have been concerned with providing guidance related to the resolution of some of the problems identified, such as the problem of consistency in judgement, comparability of safety goals used in different industries, the relationship between criteria on different levels, and relations between criteria for level 2 and 3 PSA. In parallel, additional context information has been provided. This was achieved by extending the international overview by contributing to and benefiting from a survey on PSA safety criteria which was initiated in 2006 within the OECD/NEA Working Group Risk. Finally, a separate report has been issued providing general guidance concerning the formulation, application and interpretation of probabilistic criteria. The results from the project can be used as a platform for discussions at the utilities on how to define and use quantitative safety goals. The results can also be used by safety authorities as a reference for risk-informed regulation. The outcome can have an impact on the requirements on PSA, e.g., regarding quality, scope, level of detail, and documentation. Finally, the results can be expected to support on-going activities concerning risk-informed applications.
机译:核电厂的概率安全评估(PSA)的结果是定性和定量结果的组合。定量结果通常表示为核心损坏频率(CDF)和不可接受的放射性释放频率。为了判断PSA结果的可接受性,需要定义解释结果和评估其可接受性的标准。安全目标在不同国家/地区以不同方式定义,并且使用方式也不同。目前,许多国家正在将它们与运行中的核电厂(NPP)和新设计的风险知情监管转移有关。但是,如何定义和使用概率安全性标准并非不言而喻。一方面,经验表明,安全目标是解释概率安全评估(PSA)结果的有价值的工具,并且它们往往会增强风险评估的真实性。另一方面,通常避免严格使用概率标准。一个主要问题是PSA模型中存在大量不同的不确定性,这使得难以证明其符合概率标准。此外,已经发现,由于范围的扩大,修订后的操作经验数据,方法的开发或详细程度的提高,PSA结果会随时间发生很大变化,主要是导致计算风险的频率增加。这可能会导致判断不一致的问题。该项目的第一阶段(2006年)对核电厂的概率安全目标,与安全目标的定义和应用有关的重要概念以及芬兰和瑞典的经验进行了一般性描述。第二阶段,第三阶段和第四阶段(2007-2009年)一直致力于为解决某些已确定的问题提供指导,例如判断的一致性问题,不同行业使用的安全目标的可比性,不同级别的标准,以及2级和3级PSA标准之间的关系。同时,还提供了其他上下文信息。实现这一目标的方法是,通过促进和受益于PSA安全标准调查(该调查于2006年在OECD / NEA工作组风险范围内开展)而扩展了国际视野。最后,另外发表了一份报告,提供了有关概率标准的制定,应用和解释的一般指导。该项目的结果可以用作公用事业机构讨论如何定义和使用定量安全目标的平台。该结果也可以被安全机构用作风险相关法规的参考。结果可能会对PSA的要求产生影响,例如,有关质量,范围,详细程度和文档方面的要求。最后,可以预期结果将支持正在进行的有关风险告知应用程序的活动。

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