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GB/T 41090-2021 English PDF

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GB/T 41090-2021: General design requirements of pressurized water reactor nuclear power plants with active safety systems
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Basic data

Standard ID GB/T 41090-2021 (GB/T41090-2021)
Description (Translated English) General design requirements of pressurized water reactor nuclear power plants with active safety systems
Sector / Industry National Standard (Recommended)
Classification of Chinese Standard F65
Word Count Estimation 25,214
Issuing agency(ies) State Administration for Market Regulation, China National Standardization Administration

GB/T 41090-2021: General design requirements of pressurized water reactor nuclear power plants with active safety systems


---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.
General design requirements of pressurized water reactor nuclear power plants with active safety systems ICS 27:120:20 CCSF65 National Standards of People's Republic of China General design requirements for PWR nuclear power plants with active safety systems Published on 2021-12-31 2022-07-01 Implementation State Administration for Market Regulation Released by the National Standardization Administration directory Preface I 1 Scope 1 2 Normative references 1 3 Terms and Definitions 1 4 Nuclear Power Plant Design Objective 3 5 General design requirements for nuclear power plants4 6 General design requirements for professional fields10 Reference 21

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 Nuclear Power Engineering Co:, Ltd: The main drafters of this document: Xing Ji, Yuan Xia, Fan Li, Zhang Xueshuang, Li Hui, Li Chong: General design requirements for PWR nuclear power plants with active safety systems

1 Scope

This document specifies the basic requirements for the overall design of an active safety system pressurized water reactor nuclear power plant (hereinafter referred to as "nuclear power plant") to ensure that it can be to operate safely and reliably: This document is applicable to newly-built pressurized water reactor nuclear power plants with active safety systems:

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 6249 Nuclear Power Plant Environmental Radiation Protection Regulations GB 11806 Regulations for Safe Transport of Radioactive Materials GB 18871 Basic standard for ionizing radiation protection and radiation source safety NB/T:20035 Classification of working conditions of pressurized water reactor nuclear power plants HAD002/01-2019 Emergency Preparedness and Emergency Response of Operating Organizations of Nuclear Power Plants HAF102 Nuclear power plant design safety regulations

3 Terms and Definitions

The following terms and definitions apply to this document: 3:1 safety system safetysystem Systems important to safety to ensure safe shutdown of the reactor, to remove residual heat from the core or to limit anticipated operational and design basis events the consequences of this: [Source: HAF102-2016, Glossary Explanation] 3:2 activesafetysystem Active systems used to ensure safe shutdown of the reactor, to remove residual heat from the core, or to limit the consequences of anticipated operational events and design basis accidents: [Source: GB/T 35730-2017, 3:3, with modifications] 3:3 Active Safety Systems Pressurized Water Reactor Nuclear Power Plantspressurizedwaterreactornuclearpowerplantswithactivesafetysystems Pressurized water reactor nuclear power plants that mainly rely on the active safety system to complete all safety functions in the design basis accident: Note: referred to as "energy nuclear power plant": [Source: GB/T 35730-2017, 3:4, with modifications] 3:4 safetyfunction To ensure that a facility or activity can prevent and mitigate the radiological consequences of normal operation of a nuclear power plant, anticipated operational transients and accident conditions,

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