Innovation在核反应堆安全和风险方面的需求

F. D’Auria, R. Duffey
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引用次数: 0

摘要

经过四分之三个世纪的核裂变生产能源,核反应堆安全和风险构成了一个成熟的技术部门。一个关键特征是随着新发现和知识的进步而不断更新,从而产生了广泛而详细的安全方法,这些方法仍然没有得到国际认可,普遍适用或技术上一致。每个国家都制定了自己的方法、指南、传统和要求来处理不断变化的设计、安全、选址和许可问题。在事故中的核辐射暴露与流行病中的病毒感染以及对"未知"的恐惧之间,社会风险认知存在明显的相似之处。不幸的是,在过去的二三十年里,那些对核裂变发电最早的发展贡献最大的国家越来越少地采用核裂变发电,这也打破了新的科学进步和现有安全方法改进之间的联系。通过研究核技术的起源和基础,我们考虑了以下确定性和概率性的主题:a)冷却剂损失分析;B)核燃料事故性能弱点;C)安全壳和最终散热器的作用;D)剩余风险和应急系统部署,e)独立和风险知情的决策评估。作为一项关键成果,我们建议修改传统的许可方法,并将主动和/或被动系统的使用纳入更广泛的工程安全特性管理流程。此外,我们强调需要将“尽可能低”原则与证明核设施安全性的分析联系起来,最大限度地减少对过度“纸面”安全分析和许可工作的需要。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Innovation needs in nuclear reactor safety and risk
After three quarters of a century using nuclear fission to produce energy, Nuclear Reactor Safety and Risk constitutes an established technological sector. A key feature is continuous updating following new discoveries and progress in knowledge, resulting in extensive and elaborate safety methodologies, which are still not internationally accepted, generally applicable or technically consistent. Each country developed its own methods, guides, traditions and requirements to deal with evolving design, safety, siting and licensing issues. There is a clear parallel in societal risk perception between nuclear radiation exposure in accidents and viral infection in pandemics and the fear of the “unknown”. Unfortunately, over the last 20–30 years the declining introduction of electricity by nuclear fission in the countries that contributed most to its earliest development also has broken the bond between new scientific advancements and improvements of existing safety methodologies. By looking at the origins and fundaments of nuclear technology, we consider the following topics of both deterministic and probabilistic interest: a) Loss of Coolant analysis; b) nuclear fuel accident performance weaknesses; c) role of containment and ultimate heat sinks; d) residual risk and emergency system deployment, and e) independent and risk informed decision making assessment. As a key outcome, we propose modifying the traditional licensing methodology, and the use of active and/or passive systems by being subsumed into a broader Engineered Safety Features Management process. Furthermore, we emphasize the need of connecting the As Low As Reasonably Achievable principle with the analyses to demonstrate the safety of nuclear installations minimizing the need for excessive “paper” safety analyses and licensing efforts.
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