田湾核电站反应堆压力容器应力强度因子研究

Research on the Stress Intensity Factor of Tianwan Nuclear Power Plant Reactor Pressure Vessel

针对田湾核电站反应堆压力容器材料构件的应力强度因子参数,分别采用了俄罗斯制定的ПНАЭГ-7-002-86方法和笔者提出的计算方法进行了计算分析与比较论证。获得了如下结论:对于相同的试验工况,提出的应力强度因子计算方法与俄罗斯ПНАЭГ-7-002-86计算方法相当,比其数值略大。这是由于考虑了裂纹尖端的塑性变形特性,从影响裂纹尖端物理场的角度提出了应力强度因子的计算方法,从而导致此计算方法更为保守安全。

According to the stress intensity factor parameters of reactor pressure vessel material components of Tianwan Nu-clear Power Station, the calculation and analysis of the method of IIHA3r - 7 - 002 - 86 developed by Russia and the calculation method are carried out respectively. The results are as fol lows： fo r the same experimental conditions, the calculation method of stress intensity factor is equivalent to that of Russia IIHA3r - 7 - 002 - 86, which is sl ightly larger than its value. This is due to the consideration of the plastic deformation characteristics of the crack tip and the calculation method of the stress intensity factor from the point of view of influencing the physical field of the crack tip, leading to a more conservative and safe calculation method.