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GB/T 41586-2022 English PDF

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GB/T 41586-2022: Basic input parameters and output results for emergency assessment of nuclear power plant
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PDF similar to GB/T 41586-2022


Standard similar to GB/T 41586-2022

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Basic data

Standard ID GB/T 41586-2022 (GB/T41586-2022)
Description (Translated English) Basic input parameters and output results for emergency assessment of nuclear power plant
Sector / Industry National Standard (Recommended)
Classification of Chinese Standard F70
Word Count Estimation 9,996
Issuing agency(ies) State Administration for Market Regulation, China National Standardization Administration

GB/T 41586-2022: Basic input parameters and output results for emergency assessment of nuclear power plant


---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.
Basic input parameters and output results for emergency assessment of nuclear power plant ICS 27.120 CCSF70 National Standards of People's Republic of China Basic input parameters and output results of nuclear power plant emergency assessment powerplant Published on 2022-07-11 2023-02-01 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 Overview 2 5 Basic input parameters of emergency assessment 2 5.1 Static parameters 2 5.2 Dynamic Parameters 2 6 Emergency Evaluation Output Results 3 6.1 Core damage evaluation results 3 6.2 Estimated results of airborne release source terms 3 6.3 Environmental consequences assessment results 3 6.4 Analysis results of protective actions 4

foreword

This 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. 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. China Institute of Radiation Protection, Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., National Nuclear Emergency Response Technical Support Support Center, Fujian Fuqing Nuclear Power Co., Ltd., Suzhou Thermal Research Institute Co., Ltd., and Institute of Nuclear Industry Standardization. The main drafters of this document. Yang Yapeng, Zhang Jiangang, Feng Zongyang, Jia Linsheng, Wang Xuan, Jin Li, Zhao Feng, Guo Li, Liang Boning, Wang Ning, Du Fenglei, Pu Xiang, Gao Shengqin, Zhai Liang, Cheng Youying, Liu Lipo, Dong Fangfang, Yu Haoyang. Basic input parameters and output results of nuclear power plant emergency assessment

1 Scope

This document specifies the content requirements for basic input parameters and output results required for emergency assessment of PWR nuclear power plants. This document is applicable to core damage assessment, airborne release source item estimation, and environmental consequence assessment under emergency conditions in pressurized water reactor nuclear power plants (only for Airborne release route) and emergency protective action analysis.

2 Normative references

The 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 18871-2002 Basic standard for ionizing radiation protection and radiation source safety GB/T 41582 Rapid estimation method for accident source term of nuclear power plant GB/T 41583 Nuclear Power Plant Core Damage Evaluation Method

3 Terms and Definitions

The terms and definitions defined in GB 18871-2002 and the following terms and definitions apply to this document. 3.1 protectiveaction An intervention to avoid or reduce the exposure of members of the public to exposures in situations of continuous or emergency exposure. [Source. GB 18871-2002, J6.6] 3.2 Expected dose projecteddose The dose expected to be received if no protective or remedial action is taken. [Source. GB 18871-2002, J6.8] 3.3 Preventable dose of averagedose The dose reduced by taking protective action, that is, the dose expected to be received if protective action is taken and the dose not taking protective action The difference between the doses expected to be received under the circumstances. [Source. GB 18871-2002, J6.9] 3.4 Residual dose residualdose The dose expected to exist after all protective measures have been completed (or when it is decided not to take any protective measures). 3.5 Assess the potential environmental radiation consequences of the release of radioactive material to the environment under nuclear power plant accident conditions.

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