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APPLICATION OF THE STRUCTURAL RELIABILITY METHODS FOR JUSTIFICATION OF PRESSURE REDUCTION OF PERIODIC HYDROSTATIC TEST FOR PRIMARY CIRCUIT OF NPP WWER-1000

机译:结构可靠度方法在确定NPP WWER-1000主回路周期性水压试验压力降的合理性中的应用

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An analysis is formulated to determine how reductions in test pressures change the effectiveness of hydraulic strength tests (HT). The analysis is applied to Series 1000 Water-Water Energetic Reactor (WWER-1000) nuclear power plants (NPP) operating in countries of the former Soviet Union. During periodic HT for these reactors, the applied pressure exceeds the pressure for the normal operation mode (NOM) by a factor of more than 1.5. These HT pressures are among the highest in the nuclear industry. It is desirable to reduce the HT pressure in order to minimize potential damage to equipment due to pressurization during the tests. To justify a reduction in the HT pressure, a quantitative, risk-informed assessment of HT effectiveness for changes in HT pressures has been performed. This assessment follows the guidelines of INSAG-25 [1]. A deterministic analysis is used to calculate the HT minimum temperature, based on the estimation of the damage caused by HT and the evaluation of the warm prestressing effect. A probabilistic analysis is used to estimate the change in the probability of equipment fracture caused by a reduction in the HT pressure. The probabilistic analysis assumes that HT is performed as a destructive control method for replaceable components, so that HT combined with replacement or repair of defective components increases their reliability. A simple probabilistic analysis method, based on an exponent distribution law for defect depth and a lognormal law for the defect aspect ratio, taking into account laws for defect growth, has been proposed. The fracture probability is calculated as the proportion of defects that exceed critical sizes for NOM and HT. Limit load models are used for the determination of the critical size of defects. The variation in reliability is calculated as the difference between fracture probability during NOM after HT at routine and reduced pressures. The calculation results make it possible to analyze the effect of HT pressure reduction for WWER-1000 NPPs.
机译:进行分析可以确定测试压力的降低如何改变水力强度测试(HT)的有效性。该分析适用于在前苏联国家运营的1000系列水-水能反应堆(WWER-1000)核电站(NPP)。在对这些反应堆进行定期HT期间,施加的压力比正常运行模式(NOM)的压力大1.5倍以上。这些高温压力是核工业中最高的压力之一。希望降低HT压力,以最大程度地减少测试过程中由于加压而对设备造成的潜在损害。为了证明降低HT压力的合理性,已对HT压力变化的HT有效性进行了定量,基于风险的评估。该评估遵循INSAG-25的准则[1]。基于对HT造成的破坏的估计以及对预应力的热影响的评估,使用确定性分析来计算HT的最低温度。概率分析用于估计由HT压力降低引起的设备破裂概率的变化。概率分析假定HT作为可替换组件的破坏性控制方法,因此HT与缺陷组件的替换或修理相结合可提高其可靠性。提出了一种简单的概率分析方法,该方法基于缺陷深度的指数分布定律和缺陷长宽比的对数正态定律,并考虑了缺陷增长的规律。断裂概率计算为超出NOM和HT临界尺寸的缺陷比例。极限载荷模型用于确定缺陷的临界尺寸。可靠性的变化计算为常规温度下HT后NOM期间的断裂概率与减压之间的差。计算结果使分析WWER-1000核电厂HT压力降低的效果成为可能。

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