GB/T 9225: Evolution and historical versions
| Standard ID | Contents [version] | USD | STEP2 | [PDF] delivered in | Standard Title (Description) | Status | PDF |
| GB/T 9225-2022 | English | RFQ |
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3 days [Need to translate]
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Application guidelines of reliability analysis in nuclear power generating station systems and other nuclear facilities
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GB/T 9225-2022
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| GB/T 9225-1999 | English | RFQ |
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13 days [Need to translate]
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General principles of reliability analysis for nuclear power plant safety systems
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GB/T 9225-1999
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| GB/T 9225-1988 | English | RFQ |
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General principles of reliability analysis of nuclear reactor protection systems
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GB/T 9225-1988
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PDF similar to GB/T 9225-2022
Basic data | Standard ID | GB/T 9225-2022 (GB/T9225-2022) | | Description (Translated English) | Application guidelines of reliability analysis in nuclear power generating station systems and other nuclear facilities | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F09 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 109,188 | | Date of Issue | 2022-12-30 | | Date of Implementation | 2023-07-01 | | Older Standard (superseded by this standard) | GB/T 9225-1999 | | Issuing agency(ies) | State Administration for Market Regulation, China National Standardization Administration | GB/T 9225-2022: Application guidelines of reliability analysis in nuclear power generating station systems and other nuclear facilities
---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.
ICS 27.120.20
CCSF83
National Standards of People's Republic of China
Replacing GB/T 9225-1999
Reliability of nuclear power plant systems and other nuclear facilities
Analysis Application Guide
Posted on 2022-12-30
2023-07-01 Implementation
State Administration for Market Regulation
Released by the National Standardization Management Committee
table of contents
Preface I
1 Scope 1
2 Normative references 1
3 Terms and Definitions 1
4 Abbreviations 3
5 Purpose and method 4
6 Qualitative Analysis Principles 7
7 Principles of Quantitative Analysis 17
8 Data Acquisition and Application 38
9 Applications of Reliability Methods 50
Appendix A (informative) Illustrative example 62
Appendix B (Informative) Data Program 96
Appendix C (informative) Mean time to repair97
References 102
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 for Standardization Documents"
drafting.
This document replaces GB/T 9225-1999 "General Principles for Reliability Analysis of Nuclear Power Plant Safety Systems", and is consistent with GB/T 9225-1999
In addition to structural adjustments and editorial changes, the main technical changes are as follows.
a) The definitions of the terms "availability", "reliability", "failure", "common cause failure" and "test interval time" were revised (see Chapter 3,.1999
Chapter 3 of the annual edition);
b) Added abbreviations (see Chapter 4);
c) Added the severity\\occurrence\\detectability classification of FMEA (see 6.2.3);
d) Added the application of reliability analysis method and example "Monte Carlo method" (see 9.6, Appendix A).
Please note that some contents of this document may refer to patents. The issuing agency of this document assumes no responsibility for identifying patents.
This document is proposed and managed by the National Nuclear Instruments Standardization Technical Committee (SAC/TC30).
This document is drafted by. China Nuclear Power Engineering Co., Ltd., China Nuclear Power Research and Design Institute.
The main drafters of this document. Xing Ji, Xu Simin, Huang Suwen, Chen Xiyu, Du Dejun, Chen Rigang, Zhang Yufeng, Wang Shuo, Feng Jia, Chen Peng,
Zhong Sijie, Wang Lin.
The release status of previous versions of this document and the documents it replaces are as follows.
--- First published as GB/T 9225-1988 in 1988, first revised in.1999;
--- This is the second revision.
Reliability of nuclear power plant systems and other nuclear facilities
Analysis Application Guide
1 Scope
This document provides design and operation personnel of nuclear power plant safety systems and relevant management departments for the reliability and safety of nuclear power plant safety systems.
General methods and steps of usability analysis.
This document is applicable to the qualitative and quantitative analysis of the reliability of the safety system of nuclear power plants, and is applicable to each stage of the life cycle of the safety system of nuclear power plants.
stage.
The qualitative and quantitative analysis principles of this document are applicable to the analysis of the impact of component failures on system reliability.
The general reliability and availability analysis methods in this document are applicable to structures, systems and components of nuclear power plants and other nuclear facilities.
2 Normative references
The contents of the following documents constitute the essential provisions of this document through normative references in the text. Among them, dated references, only
The version corresponding to this date applies to this document; for undated references, the latest version (including all amendments) applies to this document.
GB/T 7163 Nuclear Power Plant Safety System Reliability Analysis Requirements
GB/T 13284.1 Nuclear Power Plant Safety System Part 1.Design Criteria
3 Terms and Definitions
The following terms and definitions apply to this document.
3.1
availability availability
Under the premise of obtaining the required external resources, an item or system executes its specifications at a given moment or within a given period of time under specified conditions
Ability to define functions.
Note. Availability is divided into steady-state availability and transient availability.
3.2
steady-state availability steady-state availability
The fraction of time that an item (or system) is expected to perform satisfactorily in long-term operation.
Note. The availability of repairable items can be classified as long-term steady-state availability.
3.3
reliability reliability
The probability that an item will perform a required function in a given state and within a given time interval (mission time).
3.4
fault fault/failure
failure failure
Loss of the ability of a structure, system or component to perform its function within the acceptance criteria.
Note. The failure may be not indicated and not detected before the next test (unindicated failure), or it may be indicated and detected by some method when it occurs.
Detected (indicated fault).
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