Optimization for PWR system overpressure analysis standard

Too much standards are used in the nuclear power plant design area and compatibility issues are introduced by mixed applying of domestic standards and international standards. As the self-developed nuclear power plants are gradually exported to other countries, it is becoming more and more urgent to establish a unified system of standards and regulations. The reactor coolant pressure boundary is the second safety barrier of the reactor and preventing overpressure failure under various operation conditions is a key to ensure nuclear safety. The requirements for system over-pressure analysis in ASME and RCC-M are emphatically analyzed. The relations between system overpressure analysis criteria and mechanical stress analysis criteria are studied. The differences between overpressure analysis standards in United States, France and China are compared and analyzed. Referring to the international standards, suggestions on the optimization for existing domestic system overpressure analysis standards are presented in following three aspects: condition classification, criteria determination and analysis method. (authors)