GB/T 16702.1-2025
ActiveDesign specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 1: General principle
压水堆核电厂核岛机械设备设计规范 第1部分：总则
Application Summary AI generated
This standard establishes the general design principles, safety requirements, and technical criteria for mechanical components within the nuclear island of pressurized water reactor (PWR) nuclear power plants. It is applied by engineers and manufacturers to ensure the structural integrity, reliability, and safety of equipment such as reactor pressure vessels, piping, and pumps under normal operation and accident conditions. The standard serves as the foundational framework for subsequent detailed design specifications in the GB/T 16702 series.
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