GB/T 16702.3-2025
ActiveDesign specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 3: Class 2 components
压水堆核电厂核岛机械设备设计规范 第3部分：2级设备
Application Summary AI generated
This standard specifies the design requirements for Class 2 mechanical components within the nuclear island of pressurized water reactor (PWR) nuclear power plants, covering materials, load conditions, stress limits, and fatigue analysis. It is applied by engineers and manufacturers to ensure the structural integrity and safety of components such as certain valves, pumps, and piping systems that are important to safety but not classified as the highest safety class. The standard is used during the design and qualification phases for nuclear power plant equipment in China.
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