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Glossary of terms of instrumentation and control for nuclear power plants
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GB/T 41143-2021
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Basic data | Standard ID | GB/T 41143-2021 (GB/T41143-2021) | | Description (Translated English) | Glossary of terms of instrumentation and control for nuclear power plants | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F80 | | Word Count Estimation | 45,480 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration |
GB/T 41143-2021: Glossary of terms of instrumentation and control for nuclear power plants---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.
Glossary of terms of instrumentation and control for nuclear power plants
ICS 27:120:01
CCSF80
National Standards of People's Republic of China
Nuclear Power Plant Instrumentation and Control Terminology
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 Design and operation of nuclear power plants 1
4 Instrumentation and control systems and equipment 8
4:1 Instrumentation and control systems 8
4:2 Equipment and components of instrumentation and control systems 10
4:3 Radiation Monitoring Devices 12
5 Computer Applications 13
6 Human-machine interface 16
7 Identification and Aging Management 18
7:1 Equipment qualification 18
7:2 Aging Management 22
8 Testing and maintenance 23
8:1 Test 23
8:2 Maintenance 26
Reference 28
index 30
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 Instrument Standardization Technical Committee:
This document is drafted by: China General Nuclear Power Research Institute Co:, Ltd:, Institute of Nuclear Industry Standardization:
The main drafters of this document: Zhou Zhou, Yang Jiewei, Jiao Liling, Du Jian, Liang Xueyuan, He Wenkai, Wu Tao, Luo Dingnan, Li Dongyi, Xiong Guohua,
Li Jianbo, Zhang Wei, Weng Wenqing, Wang Li, Li Derui, Zhao Youyou:
Nuclear Power Plant Instrumentation and Control Terminology
1 Scope
This document defines the nuclear power plant instrumentation and controls (I
This document is applicable to various activities related to nuclear power plants, and other nuclear facilities can be used for reference:
2 Normative references
There are no normative references in this document:
3 Design and operation of nuclear power plants
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
design basis
The various operating conditions and events that are fully considered in accordance with established criteria in the design of structures, systems, components and equipment of a facility
range of conditions so that the facility can withstand these conditions and events without exceeding regulatory limits:
3:4
Assume the originating event postulatedinitiatingevent; PIE
Hypothetical events identified during design that may lead to expected operational events or accident conditions:
3:5
Anticipated operation event anticipatedoperationaloccurrence; AOO
Various operating processes that deviate from normal operation at least once during the operating life of a nuclear power plant;
Measures should be taken so that such events will not cause serious damage to items important to safety, nor will they lead to accident conditions:
3:6
design basis event designbasisevent; DBE
A hypothetical initiating event used in the design to determine acceptable performance requirements for a structure, system or component:
3:7
Design basis accident designbasisaccident; DBA
Hypothetical accidents leading to accident conditions in nuclear power plants:
Note 1: The nuclear power plant is designed according to established design criteria and conservative methods:
NOTE 2 The releases of radioactive material from these incidents were within acceptable limits:
3:8
Design extension conditions designextensionconditions; DEC
Accident conditions that are considered in the design process according to the best estimation method and are not considered in the design basis accident:
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