GB/T 13976-2021 English PDFUS$309.00 ยท In stock
Delivery: <= 4 days. True-PDF full-copy in English will be manually translated and delivered via email. GB/T 13976-2021: Radioactive source term of pressurized water reactor nuclear power plant for operation states Status: Valid GB/T 13976: Historical versions
Basic dataStandard ID: GB/T 13976-2021 (GB/T13976-2021)Description (Translated English): Radioactive source term of pressurized water reactor nuclear power plant for operation states Sector / Industry: National Standard (Recommended) Classification of Chinese Standard: F72 Word Count Estimation: 16,138 Issuing agency(ies): State Administration for Market Regulation, China National Standardization Administration GB/T 13976-2021: Radioactive source term of pressurized water reactor nuclear power plant for operation states---This is a DRAFT version for illustration, not a final translation. Full copy of true-PDF in English version (including equations, symbols, images, flow-chart, tables, and figures etc.) will be manually/carefully translated upon your order. Radioactive source term of pressurized water reactor nuclear power plant for operation states ICS 27:120:10 CCSF72 National Standards of People's Republic of China Replacing GB/T 13976-2008 Radioactive Source Items in Operational State of Pressurized Water Reactor Nuclear Power Plants operationstates Published on 2021-12-31 2022-07-01 Implementation State Administration for Market Regulation Released by the National Standardization Administration directory Preface III 1 Scope 1 2 Normative references 1 3 Terms and Definitions 1 4 General Requirements 2 5 General Principles for Analysis of Effluent Emission Source Items 2 6 Tritium source term analysis criteria 2 7 14C Source Term Analysis Criterion 3 8 Criterion for source term analysis of fission products and corrosion activation products 3 Appendix A (Informative) Analysis Framework for Source Items of Effluent from Pressurized Water Reactor Nuclear Power Plants 7 Appendix B (Informative) Expected Leak Rates for Major Systems and Equipment10 Appendix C (Informative) Fission Product Escape Rate Coefficient of Spent Fuel Assemblies11 Reference 12 forewordThis document is in accordance with the provisions of GB/T 1:1-2020 "Guidelines for Standardization Work Part 1: Structure and Drafting Rules of Standardization Documents" drafted: This document replaces GB/T 13976-2008 "Radioactive Source Items in the Operating State of Pressurized Water Reactor Nuclear Power Plant", and GB/T 13976-2008 In contrast, except for structural adjustments and editorial changes, the main technical changes are as follows: --- Changed the scope of application of the document, the scope of application of the document is no longer limited to U-tube steam generator pressurized water reactor nuclear power plants (see Chapter 1, Chapter 1 of the:2008 edition); --- Added the relevant content of the tritium source term analysis criteria (see Chapter 6); --- Added the relevant content of the 14C source term analysis criteria (see Chapter 7); --- Changed the method for calculating the specific activity of radionuclides in the main fluid (see Chapter 4 of 8:1, 8:2,:2008 edition); --- Added analysis criteria for emission source items of fission products and corrosion activation products (see 8:3, 8:4): Please note that some content of this document may be patented: The issuing agency of this document assumes no responsibility for identifying patents: This document is proposed and managed by the National Nuclear Energy Standardization Technical Committee (SAC/TC58): This document is drafted by: Shanghai Nuclear Engineering Research and Design Institute Co:, Ltd: The main drafters of this document: Qiu Zhongming, Mei Qiliang, Fu Yaru, Mao Lanfang, Sun Dawei, Li Hui, Ding Qianxue, Gao Shengqin, Ding Hongchun, Zhou Yan: The previous versions of this document and its superseded documents are as follows: ---First published in:1992 as GB/T 13976-1992, first revised in:2008; ---This is the second revision: Radioactive Source Items in Operational State of Pressurized Water Reactor Nuclear Power Plants1 ScopeThis document specifies the general principles for the analysis of effluent emission source terms under the operating state of pressurized water reactor nuclear power plants, as well as tritium, 14C, fission products and Emission source term analysis criteria for corrosion activation products: This document applies to the evaluation of annual releases of radionuclides to the environment through liquid and gaseous effluents from pressurized water reactor nuclear power plants:2 Normative referencesThe contents of the following documents constitute essential provisions of this document through normative references in the text: Among them, dated citations documents, only the version corresponding to that date applies to this document; for undated references, the latest edition (including all amendments) applies to this document: GB 6249 Nuclear Power Plant Environmental Radiation Protection Regulations3 Terms and DefinitionsThe following terms and definitions apply to this document: 3:1 operationalstates A general term for two states of normal operation and expected operation events: 3:2 normal operation The operation of a nuclear power plant within specified operating limits and conditions: 3:3 Anticipated operation events anticipatedoperationaloccurrences Various operations that are expected to occur at least once during the operating life of a nuclear power plant and deviate from normal operation without causing damage to items important to safety Process: 3:4 chemical waste chemicalwaste Liquids with high levels of detergents, regenerants or other chemicals: NOTE: This liquid comes mainly from decontamination systems, resin regeneration wastewater, and laboratory wastewater: 3:5 Detergentwaste of washing waste Liquids containing detergents, soaps or similar organic substances: Note: This liquid is mainly from laundry water, personnel shower water, and decontamination waste liquids of those equipment with low levels of radioactivity: 3:6 Hydrophobic floordrains Tritium-free, oxygen-containing, high-conductivity, non-primary coolant-quality liquids: Note: This liquid mainly comes from the plant sewage collection pit, ground drain and sampling station drain: ......Tips & Frequently Asked Questions:Question 1: How long will the true-PDF of GB/T 13976-2021_English be delivered?Answer: Upon your order, we will start to translate GB/T 13976-2021_English as soon as possible, and keep you informed of the progress. 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Otherwise, follow the normal steps: Add to Cart -- Checkout -- Select your currency to pay.Question 5: Should I purchase the latest version GB/T 13976-2021?Answer: Yes. Unless special scenarios such as technical constraints or academic study, you should always prioritize to purchase the latest version GB/T 13976-2021 even if the enforcement date is in future. Complying with the latest version means that, by default, it also complies with all the earlier versions, technically. |
