GB/T 13976-2008 in English

《GB/T 13976-2008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，主管部门为国家标准化管理委员会。
本标准规定了压水堆核电厂运行状态下一次冷却剂、蒸汽发生器炉水和蒸汽内放射性核素比活度的确定方法及液态流出物和气态流出物源项的确定方法。本标准计算的源项适用于评价通过液态和气态流出物释放到环境中去的放射性核素的年平均排放量。本标准采用的数据是基于使用锆包壳二氧化铀燃料的压水堆核电厂。本标准仅适用于采用U型管式蒸汽发生器的压水堆核电厂。本标准参考了美国核协会制定的美国国家标准ANSI/ANS-18.1:1984、美国核管会的技术文件NUREG-0017：1985以及IAEA的TRS No.421。
本标准代替GB/T 13976-1992《压水堆核电厂运行工况下的放射性源项》。
本标准与GB/T 13976-1992相比主要变化如下：
――标准名称改为《压水堆核电厂运行状态下的放射性源项》；
――删除了原术语“3.2 活化气体、3.13 放射性物质释放率”；增加了“正常运行”、“预计运行事件”、“水活化产物”的术语和定义；
――原“3.1 运行工况”改为“3.1 运行状态”，对部分术语的定义进行了修改。
――删除了直流式蒸汽发生器的相关内容；
――修改了源项计算中主要设计数据、主要流体内核素比活度数据、调整因子的参数值和未经处理的洗涤废液放射性物质向环境的释放率数据；
――增加了碳-14的源项。

1 Scope

This standard specifies the determination methods of primary coolant, steam generator boiler water and radionuclide specific activity in steam and the determination methods of liquid effluent and gaseous effluent source terms.
The calculated source term of this standard is applicable to assess the annual mean emission of radionuclide released to environment through liquid and gaseous effluents.
The adopted data of this standard is based on the pressurized-water reactor nuclear power plant using zirconium cladding uranium dioxide fuel.
This standard is only applicable to the pressurized-water reactor nuclear power plant adopting U-pipe steam generator.

2 Normative References

The following normative documents contain provisions which, through reference in this standard, constitute provisions of this standard. For dated reference, subsequent amendments to, or revisions of, any of these publications do not apply. However, all parties coming to an agreement according to this standard are encouraged to study whether the latest edition of these documents is applicable. For undated references, the latest edition of the normative document referred to applies. For undated references, the latest edition is applicable to this standard.

Contents
Foreword I
1 Scope
2 Normative References
3 Terms and Definition
4 Calculation Methods for Radionuclide Specific Activity in Main Fluid
5 Source Terms of Radionuclide Effluents
Annex A (Normative) Main Design Parameter of Referred Nuclear Power Plant
Annex B (Normative) System Flow Diagram and Nuclide Removal Way of Referred Nuclear Power Plant
Annex C (Normative) Classification of Radionuclide
Annex D (Normative) Specific Activity of Radionuclide in Main Fluid of Referred Nuclear Power Plant
Annex E (Normative) Calculation Formula of Adjustment Factor in Nuclear Power Plant
Annex F (Normative) Parameter Value for Determining Adjustment Factor in Nuclear Power Plant
Annex G (Informative) Source Term of Gaseous Effluent
Annex H (Informative) Source Term of Liquid Effluent
Annex I (Informative) Release Rate of Tritium
Annex J (Informative) Release Rate of Carbon