Standard No.:	GB/T 13976-2008
English Name:	Radioactive Source Term of PWR Nuclear Power Plant for Operational States
Chinese Name:	压水堆核电厂运行状态下的放射性源项
Chinese Classification:	F72    Nuclear facilities radiation safety
Professional Classification:	GB    National Standard
ICS Classification:	27.120.10 27.120.10     Reactor engineering 27.120.10
Issued by:	AQSIQ; SAC
Issued on:	2008-07-02
Implemented on:	2009-4-1
Status:	superseded
Superseded by:	GB/T 13976-2021 Radioactive source term of pressurized water reactor nuclear power plant for operation states
Superseded on:	2022-7-1
Superseding:	GB/T 13976-1992 Radioactive source term of PWR nuclear power plant for operational states
Language:	English
File Format:	PDF
Word Count:	8000 words
Price(USD):	200.0
Delivery:	via email in 1 business day

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