GB/T 46694-2025 Active National standards

GB/T 46694-2025 Primary coolant system source terms analysis and control criteria for pressurized water reactor nuclear power plants

GB/T 46694-2025 Primary coolant system source terms analysis and control criteria for pressurized water reactor nuclear power plants

Publish Date: 2025-10-31 Implement Date: 2025-10-31 For services related to genuine standard inquiry, procurement, translation, and other related services in China, please Contact Us
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Basic Information

Standard Code: GB/T 46694-2025
Standard Type: National standards
Standard Status: Active
is_force_gb: no
CCS Name: Radiation protection and monitoring
ICS Name: Nuclear power stations, safety
Publish Date: 2025-10-31
Implement Date: 2025-10-31
Pages: 20 pages

Scope

This document specifies the analysis criteria and control requirements for radiation source terms of the primary coolant, primary circuit system equipment, and core structure materials in the design of pressurized water reactor nuclear power plants during normal operation.
This document applies to the analysis and control of radiation source terms in the primary circuit system during normal operation, as considered in the design of pressurized water reactor nuclear power plants.

Development Information

Word Count: 23 Thousand words Pages: 20 pages

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