GB/T 16702-2019

Active

Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants

压水堆核电厂核岛机械设备设计规范

Standard Type
GBT
ICS
27.120.20
CCS
F69
Status
Active
Issue Date
2019-12-31
Implementation
2020-07-01
Centralized Committee
国家标准委
Issuing Authority
国家市场监督管理总局、中国国家标准化管理委员会

Application Summary AI generated

This standard specifies the design requirements, load conditions, material selection, and stress analysis methods for mechanical components within the nuclear island of pressurized water reactor (PWR) nuclear power plants. It is applied by engineers and regulatory bodies during the design, fabrication, and safety review of critical equipment such as reactor pressure vessels, steam generators, and primary piping. The code ensures structural integrity and operational safety under normal, upset, and accident conditions in the nuclear energy 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.