严重事故情况下确定安全壳裂缝实际大小的方法

IF 0.4 4区 工程技术 Q4 NUCLEAR SCIENCE & TECHNOLOGY
O. V. Goryunov
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引用次数: 0

摘要

2 级概率风险分析 (PRA-2) 的严重事故计算需要相关的泄漏参数,如位置、面积、流量等。由于发生泄漏时的介质压力是概率性的,因此 PRA-2 要进行一系列严重事故的变式计算。然而,在假设发生泄漏时,确定泄漏的大小和位置仍然是个问题。为此,提出了一种减少 PRA-2 严重事故变量计算数量的方法,以获得符合实际的结果。根据保守假设,在衬里受力最大的区域假设出现一条贯穿裂缝,其行为将决定安全壳的最终状态。初始裂缝大小与安全壳试运行测试期间的介质泄漏量相对应。因此,可以根据对安全壳内衬应力-应变状态的评估来确定泄漏参数,而最终状态则根据线性断裂力学来确定。
本文章由计算机程序翻译,如有差异,请以英文原文为准。

Method for determining the realistic size of a crack in a containment in the case of a severe accident

Method for determining the realistic size of a crack in a containment in the case of a severe accident

Method for determining the realistic size of a crack in a containment in the case of a severe accident

Calculations of severe accidents performed for level 2 probabilistic risk analysis (PRA-2) require the relevant leakage parameters such as location, area, flow rate, etc. Since the pressure of the medium at which the leakage occurs is probabilistic, a series of variant calculations of a severe accident is performed for the PRA‑2. However, when postulating the occurrence of a leakage, determining its size and location remains problematic. In this regard, an approach is proposed for reducing the number of variant calculations of severe accidents for the PRA‑2 to obtain its realistic results. According to conservative assumptions, a single through crack in the most stressed area of the lining is postulated, whose behavior will determine the ultimate state of the containment. The initial crack size corresponds to the leakage of the medium during the commissioning tests of the containment. Leakage parameters can thus be determined based on the assessment of the stress-strain state of the containment lining, while the ultimate state is established on the basis of the linear fracture mechanics.

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来源期刊
Atomic Energy
Atomic Energy 工程技术-核科学技术
CiteScore
1.00
自引率
20.00%
发文量
100
审稿时长
4-8 weeks
期刊介绍: Atomic Energy publishes papers and review articles dealing with the latest developments in the peaceful uses of atomic energy. Topics include nuclear chemistry and physics, plasma physics, accelerator characteristics, reactor economics and engineering, applications of isotopes, and radiation monitoring and safety.
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