裂缝控制在BDBE下减轻失效后果中的应用

N. Kasahara, T. Wakai, Izumi Nakamura, Takuya Sato, M. Ichimiya
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引用次数: 0

摘要

作为福岛核电站事故的教训,业界认识到在超越设计基础事件(BDBE)之后减轻事故后果的重要性。我们提出了在BDBE下应用断裂控制来减轻核部件失效后果的概念。设计基础事件(DBE)和BDBE之间的需求是不同的。就DBE而言,它需要防止故障的发生,因此,其结构方法正在加强。另一方面,BDBE要求减轻故障后果。使用DBE的简单强化方法不适合这种BDBE需求。作为减轻破坏后果的结构加固方法,我们建议采用裂缝控制的概念。其基本思想是控制故障位置和模式的顺序。先前的故障释放负载,并防止进一步的灾难性后续故障。最后,故障的位置和模式是有限的。对各种破坏模式进行绝对强度评估并不容易,特别是对BDBE而言。然而,裂缝控制只需要在不同位置和破坏模式之间进行相对强度评估。本文讨论了该方法的两个应用实例。一个是在严重事故条件下的快堆容器。我们的方法控制液体冷却剂表面上方容器的上部比下部弱。即使在高压和高温条件下导致反应堆容器失效,这种强度控制也能保持足够的冷却剂,因为上部的结构故障会释放内部压力来保护下部。另一个例子是大地震下的管道。我们的建议控制的支撑强度弱于管道本身。当支架首先失效时,管道系统的固有频率下降。当主振型的固有频率低于地震荷载的峰值频率时,地震荷载几乎不传递给管道,避免了倒塌或断裂等灾难性破坏。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Application of Fracture Control to Mitigate Failure Consequence Under BDBE
As a lesson learned from the Fukushima nuclear power plant accident, the industry recognized the imporatance of mitigating accident consequences after Beyond Design Basis Events (BDBE). We propose the concept of applying fracture control to mitigate failure consequences of nuclear components under BDBE. Requirements are different between Design Basis Events (DBE) and BDBE. In the case of DBE, it requires preventing occurrence of failures, and thus, its structural approach is strengthening. On the other hand, BDBE requires mitigating failure consequences. The simple strengthening approach with DBE is inappropriate for this BDBE requirement. As the structural strengthening approach for mitigating failure consequences, we propose applying the concept of fracture control. The fundamental idea is to control the sequence of failure locations and modes. Preceding failures release loadings and prevent further catastrophic consequent failures. At the end, locations and modes of failure are limited. Absolute strength evaluation for each failure mode is not easy especially for BDBE. Fracture control, however, requires only relative strength evaluation among different locations and failure modes. Our paper discusses two sample applications of our proposed method. One is a fast reactor vessel under severe accident conditions. Our method controls the upper part of a vessel above the liquid coolant surface weaker than the lower part. This strength control maintains enough coolant even after a high pressure and high temperature condition causes failure of the reactor vessel because structural failure in the upper part releases internal pressure to protect the lower part. The other example is the piping under a large earthquake. Our proposal controls strength of supports weaker than the piping itself. When the supports fail first, natural frequencies of piping systems drop. When the natural frequencies of dominant modes are lower than the peak frequency of seismic loads, seismic loads hardly transfer to the piping and catastrophic failures such as collapse or break are avoided.
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