GB/T 46694-2025
ActivePrimary coolant system source terms analysis and control criteria for pressurized water reactor nuclear power plants
压水堆核电厂主回路系统源项分析及控制准则
Application Summary AI generated
This standard specifies the methods for analyzing and controlling radioactive source terms within the primary coolant system of pressurized water reactor (PWR) nuclear power plants. It is applied during the design, operation, and maintenance phases to ensure radiation safety and to minimize personnel exposure and environmental release. The criteria are used by nuclear power plant operators, safety regulators, and engineering teams to establish limits for coolant activity and to design shielding and waste treatment systems.
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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.