GB/T 13976-2021 in English
VALIDRadioactive source term of pressurized water reactor nuclear power plant for operation states
- Issued on:2021-12-31
- Implemented on:2022-07-01
- File Format:PDF
- Delivery:Via email within 1~3 business days
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《GB/T 13976-2021压水堆核电厂运行状态下的放射性源项》由TC58（全国核能标准化技术委员会）归口，TC58SC2（全国核能标准化技术委员会辐射防护分会）执行，主管部门为国家标准化管理委员会。
Introduction
Core changes in the standard revision
| Revision dimensions | 2008 version | 2021 version |
|---|---|---|
| Scope of application | U-tube steam generator only | All PWR types |
| New content | Tritium/14C not specified | Separate chapters specify tritium (Chapter 6) and 14C (Chapter 7) |
| Calculation method | Single conservative value | Dual-track system of design source term (conservative) and actual source term (actual) |
Analysis of key technical requirements
1. Tritium source term calculation system
The standard specifies six major production pathways: fuel fission (ternary fission), boron neutron reaction, and release of combustible poisons, etc., and requires the use of neutron transport programs to accurately calculate the production rate. The design source term load factor is 1.0, and the actual source term is based on actual operating data.
2. New 14C monitoring specifications
For the first time, a complete 14C analysis framework is established, focusing on monitoring: 17O(n,α)14C and 14N(n,p)14C two types of reaction pathways. The gas-liquid emission ratio is determined by the performance of the activated carbon adsorption system, with a typical value of 90% gaseous and 10% liquid.
Implementation Recommendations
Fission Product Monitoring Scheme
The design source term adopts a dose equivalent 131I activity concentration of 1-5GBq/t, and the actual source term is recommended to be controlled at 0.1GBq/t. Required supporting equipment:
- Online gamma spectrometer for primary coolant
- Kr/Xe delayed decay device for waste gas treatment system
- Spent fuel damage monitoring coefficient given in Appendix C
Background of standard evolution
With the commissioning of third-generation reactors such as AP1000 and Hualong One, the original standard can no longer cover the radioactive source term characteristics of new reactors. This revision introduces:
- Source term allocation model for non-U-tube steam generators
- Tritium release kinetics of high burnup fuel
- Migration mechanism of 14C in moderator
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