GB/T 41090-2021General design requirements of pressurized water reactor nuclear power plants with active safety systems (English PDF)
能动安全系统压水堆核电厂总设计要求
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Issued by
SAMR; SAC
Level / Type
National · Recommended
Issue date
December 31, 2021
Implementation date
July 1, 2022
Scope
GB/T 41090-2021 is the English-translated version of 能动安全系统压水堆核电厂总设计要求.
GB/T 41090-2021 sets the basic requirements for the overall design of pressurized water reactor nuclear power plants that rely mainly on active safety systems to perform all safety functions in design basis accidents, so that the plants operate safely and reliably.
It applies to newly built plants of this kind. After the terms, including safety system, active safety system and safety function, it states the design objectives of the plant, general design requirements for the whole plant and for the individual professional fields.
It refers to GB 6249 on environmental radiation protection, GB 11806 on the safe transport of radioactive material, GB 18871 on ionizing radiation protection, NB/T 20035 on the classification of plant conditions and the HAF102 design safety regulations. It was issued on 31 December 2021 and has applied since 1 July 2022.
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Document preview — GB/T 41090-2021
National Standard of the People's Republic of China
- ICS
- 27.120.20
- Classification
- F 65
Issued by: State Administration for Market Regulation; Standardization Administration of the PRC
Contents
- Preface
- 1 Scope
- 2 Normative references
- 3 Terms and Definitions
- 4 Nuclear Power Plant Design Objective
- 5 General design requirements for nuclear power plants
- 6 General design requirements for professional fields
- Reference
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.
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
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 Active safety system
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 Pressurized water reactor nuclear power plants with active safety systems
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 Safety function
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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This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 21 pages — is available in the English PDF.
Referenced standards
Normative references
- GB 6249Regulations for environmental radiation protection of nuclear power plants
- GB 11806Regulations for the safe transport of radioactive material
- GB 18871Basic Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources
- NB/T 20035Categorization of Conditions of PWR Nuclear Power Plants
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Related Standards
GB 11806-2019 — Regulations for the safe transport of radioactive material
GB 18871-2002 — Basic Standards for Protection Against Ionizing Radiation and for the Safety of Radiation Sources
GB 6249-2025 — Regulations for environmental radiation protection of nuclear power plants
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