核电机械设备国产化材料力学性能验收值确定方法研究

Study on the Method for Determining the Acceptance Value of Material Properties of Localized Material of Nuclear Power Machinical Equipment

目前,我国主要依据以RCC-M和ASME为代表的欧美核电标准规范对核电机械设备材料进行制造和验收。为建立一套适合我国工业水平和实践情况的自主化材料标准,我们需要解决关键技术问题:材料力学性能验收值的确定。本文通过对国内外已有材料力学性能验收准则确定方法、技术原理和材料性能数据处理方法的研究,提出了我国核电机械设备国产化材料力学性能验收值确定方法,并根据此方法,对反应堆压力容器堆芯段国产化材料力学性能数据进行初步统计分析,得到相关力学性能数据分布以及具有一定置信水平和超越概率的数据,为我国自主化材料标准的制定提供数据支撑。

At present,the materials of China’s nuclear power mechanical equipment are mostly manufactured and accepted in accordance with European and American nuclear power standards represented by RCC-M and ASME.In order to establish a set of independent material standards suitable for China’s industrial level and practice,key technical issues need to be resolved:determination of the acceptance value of material mechanical properties.Based on the research on the determination methods,technical principles and material performance data processing methods of existing material mechanical property acceptance criteria at home and abroad,a method was proposed used to determine the mechanical property acceptance values of domestic materials for nuclear prower machinery equipment.According to this method,a preliminary statistical analysis of the mechanical performance data of the domestically produced materials in the reactor core region of the reactor vessel was conducted to obtain the relevant mechanical performance data distribution and data with a certain level of confidence and probability of surpassing.The results of data processing contribute to provide support for the formulation of China’s independent material standards.