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
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 of GB/T 13976-2008
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
