Risk-informing Nuclear Reactor Safety: the Prediction of the Probability of Core Damage Due to Loss of Power and Cooling

Romney Duffey, E. Zio
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Abstract

The modern idea of Risk-Informed Decision-Making (RIDM) is here critically examined for all existing, advanced and Generation-IV nuclear reactor systems. Motivated by the predictive difficulties of Probabilistic Risk Assessment (PRA) in regard to occurred accidents, it is evident that the real (not hypothetical) consequences of nuclear core damage accidents that must be considered and quantified are the financial losses, infrastructure damages, societal disruptions and adverse political policies, and not solely the traditional exceedance of regulated radiation release or public exposure limits. With this perspective, a new dynamic analysis is presented for estimating the probability of core damage due to extended loss of power and cooling in a modern nuclear reactor, giving results different from current standardized PRA/PSA analyses. Using existing data, we approach the multitude of different events in a new way: whatever the initial event in the finite event set{external flood, fire, hurricane, ice storm, typhoon, earthquake, cyber attack…}, the fundamental concerns are the consequent loss and non-restoration of power, and the inadequate cooling of the core. The present proposed quantitative evaluation uses applicable and fully "exchangeable" severe event data for nuclear and non-nuclear systems, including 'active' and 'passive' emergency back-up systems for a wide range of power losses that lead to widespread damage and societal disruption. While not design-specific, this new independent "order-of-magnitude" estimate for the probability of core damage is some two to two hundred times larger than that shown or reported in recent modern and formal PSA/PRA for licensing submission using generic failure rate data rather than actual severe event data. This new finding suggests greater uncertainties exist than presently assumed for Risk-Informed Decision-Making (RIDM), and points to the need for a major reconsideration and updating of risk assessment and regulatory risk-informed approaches for nuclear plant safety evaluation.
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核反应堆安全风险信息:预测失去动力和冷却导致堆芯损坏的概率
风险知情决策(RIDM)的现代理念在此针对所有现有、先进和第四代核反应堆系统进行了严格审查。由于概率风险评估 (PRA) 在预测已发生事故方面存在困难,因此必须考虑和量化的核芯损伤事故的真正(而非假设)后果显然是经济损失、基础设施破坏、社会混乱和不利的政治政策,而不仅仅是传统的辐射释放或公众照射限值超标。从这一角度出发,我们提出了一种新的动态分析方法,用于估算现代核反应堆因长时间失去动力和冷却而导致堆芯损坏的概率,其结果不同于当前的标准化 PRA/PSA 分析。利用现有数据,我们以一种新的方式来处理多种不同的事件:无论有限事件集中的初始事件是什么(外部洪水、火灾、飓风、冰风暴、台风、地震、网络攻击......),我们关注的根本问题是随之而来的电力损失和无法恢复,以及堆芯冷却不足。目前建议的定量评估使用核与非核系统的适用和完全 "可交换 "的严重事件数据,包括 "主动 "和 "被动 "紧急备用系统,以应对导致广泛损害和社会混乱的各种电力损失。尽管并非针对特定设计,但这一新的核芯损坏概率独立 "数量级 "估算值,比最近的现代和正式 PSA/PRA 中使用通用故障率数据而非实际严重事件数据进行的许可提交所显示或报告的概率要高出约两到两百倍。这一新发现表明,存在的不确定性比目前假设的风险知情决策 (RIDM) 更大,并表明需要对核电厂安全评估的风险评估和监管风险知情方法进行重大重新考虑和更新。
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Risk-informing Nuclear Reactor Safety: the Prediction of the Probability of Core Damage Due to Loss of Power and Cooling
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