GB/T 16702.2-2025
ActiveDesign specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 2：Class 1 components
压水堆核电厂核岛机械设备设计规范 第2部分：1级设备
Application Summary AI generated
This standard specifies the design requirements for Class 1 mechanical components within the nuclear island of pressurized water reactor nuclear power plants. It is applied to safety-critical equipment such as reactor pressure vessels, primary coolant piping, and main pumps, ensuring structural integrity under extreme operating conditions. The standard serves as a mandatory technical basis for engineering design, manufacturing, and regulatory review in China's nuclear power industry.
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Transparency note: The application summary and key sentences on this page were automatically generated by AI from the standard's original text. This content has not been human-verified and should not be used for compliance or regulatory purposes. Always refer to the official standard document from the issuing authority.