GB/T 16702-1996
AbolishedDesign rules for mechanical components of PWR nuclear islands
压水堆核电厂核岛机械设备设计规范
Application Summary AI generated
This standard specifies the design rules for mechanical components within the pressurized water reactor (PWR) nuclear island, covering pressure vessels, piping, valves, and supports. It is applied in the design, construction, and safety assessment of nuclear power plant primary circuits to ensure structural integrity under operational and accident conditions. The standard is used by nuclear engineering firms and regulatory bodies in China for reactor coolant system components.
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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.