GB/T 16702.6-2025

Active

Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants—Part 6: Reactor vessel internals

压水堆核电厂核岛机械设备设计规范 第6部分:堆内构件

Standard Type
GBT
ICS
27.120.20
CCS
F69
Status
Active
Issue Date
2025-02-28
Implementation
2025-02-28
Centralized Committee
国家标准委
Issuing Authority
国家市场监督管理总局、国家标准化管理委员会

Application Summary AI generated

This standard specifies the design requirements for reactor vessel internals, including core support structures, guide tubes, and surveillance specimen holders, within pressurized water reactor nuclear power plants. It is applied by engineers and procurement professionals to ensure the mechanical integrity, safety, and performance of these components under normal operation, accident conditions, and seismic events. The standard is used in the design, manufacturing, and quality assurance processes for nuclear island equipment in the nuclear energy industry.

Related Standards

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.