Evaluation of Metal Ageing of Reactor Pressure Vessels in a Nuclear Power Plant under the Influence of Ageing Mechanisms and Environmental Conditions

Galya Dimova
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Abstract

The reactor metal in NPP is subjected to ageing mechanisms – corrosion, erosion, fatigue and neutron fluence embrittlement. These mechanisms cause degradation of the mechanical properties and may lead to the occurrence of defects. Environmental conditions are high pressure and fluid temperature values along the primary circuit. Where defects occur, it is possible to observe fracture of the metal under the environmental conditions. The RPV metal was studied by non-destructive testing methods. The article contains the results of the methods applied. In the defects site the values of fluence, circular stresses and temperatures were defined for a reactor operating under accident conditions. The impact of these factors in creating zones in the metal with risk of destruction has been considered. The results show, that corrosion and erosion have not caused defects in the metal. Neutron fluence and its thermal impact on the metal have caused embrittlement which is manifested by indications of defects. Two main factors were observed that lead to the creation of sites with a potential risk of fracture: 1) the neutron and thermal embrittlement of the metal, and 2) the hydraulic stresses from the fluid. The stress intensity factors of some defects, as well as the critical values of these factors have been calculated. The comparison of these values demonstrates that the metal in the danger zones will not be damaged.
在老化机制和环境条件影响下对核电站反应堆压力容器金属老化的评估
核反应堆中的反应堆金属会受到老化机制的影响--腐蚀、侵蚀、疲劳和中子通量脆化。这些机制会导致机械性能下降,并可能导致缺陷的出现。一次回路的环境条件是高压和流体温度值。在出现缺陷的地方,可以观察到金属在环境条件下的断裂。通过无损检测方法对 RPV 金属进行了研究。文章包含所使用方法的结果。在缺陷部位,确定了反应堆在事故条件下运行时的通量、循环应力和温度值。考虑了这些因素在金属中产生破坏风险区域的影响。结果表明,腐蚀和侵蚀并未造成金属缺陷。中子通量及其对金属的热影响造成了脆化,表现为缺陷迹象。有两个主要因素导致产生具有潜在断裂风险的部位:1) 金属的中子脆化和热脆化,以及 2) 流体的液压应力。对某些缺陷的应力强度因子以及这些因子的临界值进行了计算。这些数值的比较表明,危险区域内的金属不会受损。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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