Search result: GB/T 45569-2025
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Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
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GB/T 45569-2025
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| Standard ID | GB/T 45569-2025 (GB/T45569-2025) | | Description (Translated English) | Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants | | Sector / Industry | National Standard (Recommended) | | Classification of Chinese Standard | F69 | | Classification of International Standard | 27.120.20 | | Word Count Estimation | 26,289 | | Date of Issue | 2025-04-25 | | Date of Implementation | 2025-04-25 | | Issuing agency(ies) | State Administration for Market Regulation, National Standardization Administration |
GB/T 45569-2025.Design criteria for insulation of reactor coolant system equipment and pipelines in pressurized water reactor nuclear power plants
ICS 27.120.20
CCSF69
National Standard of the People's Republic of China
Reactor coolant system equipment for pressurized water reactor nuclear power plants and
Design criteria for pipe insulation
(ISO 23466.2020,MOD)
Released on 2025-04-25
2025-04-25 implementation
State Administration for Market Regulation
The National Standardization Administration issued
Table of contents
Preface III
1 Range 1
2 Normative references 1
3 Terms and Definitions 1
4 Universal Design Elements 1
4.1 General requirements 1
4.2 Material selection 2
4.3 Thermal performance design and test 3
4.4 Mechanical performance design and testing 4
4.5 Special requirements 5
4.6 Other requirements 6
5 Reactor Pressure Vessel (RPV) Insulation Design Requirements 6
5.1 Design requirements 6
5.2 Material selection 7
5.3 Thermal performance requirements 7
5.4 Mechanical properties and structural requirements 7
6 RCS other equipment and pipeline insulation design requirements 7
6.1 Design requirements 7
6.2 Material selection 7
6.3 Thermal performance requirements 7
6.4 Mechanical properties and structural requirements 8
Appendix A (Informative) Comparison table of structure numbers between this document and ISO 23466.2020 9
Appendix B (Informative) List of technical differences between this document and ISO 23466.2020 and their causes 11
Appendix C (Informative) Description of Metal Insulation Layer Structure 13
Appendix D (Informative) Description of non-metallic insulation layer structure 15
D.1 Brief description 15
D.2 Cassette type non-metallic insulation layer 15
D.3 Bundled non-metallic insulation layer 15
D.4 Insulation pad non-metallic insulation layer 16
Appendix E (Informative) An RPV insulation layer that performs RPV external cooling function 17
E.1 Brief description17
E.2 Design 17
Appendix F (Informative) A RPV insulation layer with radiation shielding function 19
Preface
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 is modified to adopt ISO 23466.2020 "Design criteria for insulation of reactor coolant system equipment and piping in pressurized water reactor nuclear power plants".
Compared with ISO 23466.2020, this document has many structural adjustments. Comparison table of structural number changes between the two documents
See Appendix A.
This document has many technical differences compared to ISO 23466.2020.
A single line (|) is used to indicate these technical differences. A list of these technical differences and their reasons is given in Appendix B.
The following editorial changes were made to this document.
--- In Chapter 3, the ISO and IEC international terminology reference URLs were deleted;
--- Deleted the contents in 5.2 and 6.2 that were repeated in 4.2.2;
---In Appendix C, the description of the metal insulation layer structure is unified, and the two-dimensional insulation block structure diagram is changed to a three-dimensional diagram, which is more convenient to view.
Intuitive;
--- Appendix D clarifies the types of non-metallic insulation layers and adds the description of "insulation pad" to make the content more complete;
--- The description of forced circulation reactor cavity water injection is added in Appendix E to make the form of reactor cavity water injection more complete;
--- Change the figure in Appendix F to an intuitive schematic diagram;
---Removed references.
Please note that some of the contents of this document may involve patents. The issuing organization of this document does not assume the responsibility for identifying patents.
This document was proposed and coordinated by the National Nuclear Energy Standardization Technical Committee (SAC/TC58).
This document was drafted by. China Nuclear Power Research and Design Institute, Nuclear Industry Standardization Institute.
The main drafters of this document are. Qiu Yang, Luo Ying, Hu Tian, Liu Wei, Yang Min, Wang Xuxin, Xie Guofu, Qiu Tian, Zhou Gaobin, He Jinsong, Li Yuguang,
Yu Tianda, Yu Zhiwei, Tang Chenhang, Wu Feifei, Li Jiang, and Wang Ranxu.
Reactor coolant system equipment for pressurized water reactor nuclear power plants and
Design criteria for pipe insulation
1 Scope
This document specifies the basic requirements for the design of insulation for reactor coolant system (RCS) equipment and piping in pressurized water reactor nuclear power plants.
This document is applicable to the metal insulation layer and non-metal insulation layer of RCS equipment and pipelines in pressurized water reactor nuclear power plants, and other reactor types can refer to it for implementation.
2 Normative references
The contents of the following documents constitute essential clauses of this document through normative references in this document.
For referenced documents without a date, only the version corresponding to that date applies to this document; for referenced documents without a date, the latest version (including all amendments) applies to
This document.
GB/T 4132 Thermal insulation terminology (GB/T 4132-2023, ISO 9229.2020, IDT)
GB/T 10294 Determination of steady-state thermal resistance and related properties of thermal insulation materials - Guarded hot plate method
GB/T 10296 Determination of steady-state heat transfer properties of thermal insulation layers - Circular tube method
GB/T 13475 Determination and calibration of adiabatic steady-state heat transfer properties and guarded hot box method
3 Terms and definitions
The terms and definitions defined in GB/T 4132 and the following apply to this document.
3.1
The main heat insulation material is a heat preservation layer of metal material.
3.2
The main thermal insulation material is a thermal insulation layer of non-metallic material.
3.3
Chimney effect
Air circulation between the inside and outside of the insulation layer caused by temperature differences.
4 General Design Elements
4.1 General requirements
The design of the insulation layer should comprehensively consider the requirements for achieving all its functions, and its quality assurance level and resistance should be determined according to the overall technical requirements of the nuclear power plant.
The following factors should be considered in the design of the insulation layer.
---Material selection;
--- Thermal performance design and testing;
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