NB/T 20003.8-2021Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 8: Leak testing (English PDF)
核电厂核岛机械设备无损检测 第8部分:泄漏检测
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Issued by
NEA
Level / Type
Industry · Recommended
Issue date
January 7, 2021
Implementation date
July 1, 2021
Scope
NB/T 20003.8-2021 is the English-translated version of 核电厂核岛机械设备无损检测 第8部分:泄漏检测.
NB/T 20003.8-2021 is the Chinese standard "Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 8: Leak testing". Its scope clause reads: This document specifies the technical requirements for leak testing adopted by mechanical components in nuclear island of nuclear power plants.
This document is applicable to leak testing during the manufacture and installation of mechanical components and parts in nuclear island. Its clauses include terms and definitions; general requirement.
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Document preview — NB/T 20003.8-2021
National Standard of the People's Republic of China
- Replacing
- NB/T 20003.8-2010
Issued by: National Energy Administration of the People's Republic of China
Contents
- Foreword i
- 1 Scope
- 2 Normative references
- 3 Terms and definitions
- 4 General requirement
- 5 Equipment and devices
- 6 Testing method and technique
- 7 Testing report
- Annex A (Normative) Bubble testing - Direct pressure method
- Annex B (Normative) Bubble testing - Vacuum box method
- Annex C (Normative) Testing by helium mass spectrometer - Sniffing probe method (Sniffing method)
- Annex D (Normative) Testing by helium mass spectrometer - Tracer probe method (helium spray method)
- Annex E (Normative) Testing by helium mass spectrometer - Hood method
- Annex F (Normative) Pressure change testing
- Annex G (Normative) Demonstration block for bubble method
- Annex H (Normative) Helium leak testing of steam generator tube-tube plate seal welding
1 Scope
This document specifies the technical requirements for leak testing adopted by mechanical components in nuclear island of nuclear power plants.
This document is applicable to leak testing during the manufacture and installation of mechanical components and parts in nuclear island.
2 Normative references
The following documents contain provisions which, through reference in this text, constitute provisions of this document. For dated references, only the edition cited applies. For undated references, the latest edition (including any amendments) applies.
GB/T 12604.7 Non-destructive testing - Terminology -Terms used in leak testing
NB/T 20003.1-2021 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 1: General requirements
NB/T 20003.7 Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 7: Visual testing
3 Terms and definitions
For the purposes of this document, the terms and definitions given in GB/T 12604.7 and NB/T 20003.1-2021 and the following apply.
3.1 standard leak
calibrated leak with known leakage rate to dry air (dew point temperature below -25°C) under specified conditions (inlet pressure: 100kPa ± 5kPa; outlet pressure: less than 1kPa; temperature: 23°C±7°C)
3.2 calibrated leak
leak providing a known mass flow rate for a specified gas under specified conditions
3.3 background signal
indication of stable or fluctuant output signal produced by the leak detector due to the presence of residual tracer gas or other factor that may cause response of the testing element, when no tracer gas is applied
3.4 Bourdon tube type pressure gauge
high-precision differential pressure gauge with the function of zero compensation
4 General requirement
4.1 Qualification of testing personnel
The requirements specified in 5.1 of NB/T 20003.1-2021 shall apply.
4.2 Testing documents
The testing procedures, testing process cards or other testing documents shall meet the requirements of NB/T 20003.1-2021. The leak testing shall be implemented according to effective testing procedures.
The testing procedures shall cover at least the following contents:
- - scope of application: type, size, testing range and material of the workpiece under test;
- - quoted laws, regulations, codes, standards, design documents, etc.;
- - qualification of testing personnel;
- - information of the testing piece, such as name, shape, size, testing area and volume;
- - testing equipment and devices, such as leak detector, pump, pressure gauge, vacuum gauge, standard leak, calibrated leak and tracer gas;
- - testing requirements, such as testing time, surface preparation requirements and testing methods used;
- - testing process and testing technique;
- - evaluation, recording and acceptance standard of testing results;
- - content and format of testing report.
The supplementary requirements of different leak testing methods to testing procedures shall meet the relevant requirements specified in A.1, B.1, C.1, D.1, E.1 and F.1.
4.3 Procedure demonstration
4.3.1 Scope of application
The testing procedure demonstration shall be performed under the following conditions:
- - the workpiece is subjected to the leak testing for the first time;
- - the testing conditions and/or technical requirements (specified value or numerical range of essential variables in the annex) change;
- - specified in relevant product design documents or purchase specifications.
4.3.2 Implementation of procedure demonstration
Under the testing conditions specified in the procedure, the testing personnel shall conduct leak testing on the demonstration specimen containing calibrated leak according to the requirements of the procedure. If the leakage of calibrated leak is detected, the procedure shall be considered as valid.
The above procedure shall be recorded and documented.
4.4 Testing scope and proportion
......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 22 pages — is available in the English PDF.
Referenced standards
Cited by
- GB/T 42143-2022Specification for design and construction of steel containment vessel of pressurized water reactor nuclear power plant
- NB/T 20482-2018Specification for design and construction of steel containment vessel of nuclear power plant of PWR
- NB/T 20412-2017Specification for structure module assembly and acceptance in PWR nuclear power plant
- NB/T 20413-2017Technical regulation for structural modules installation and acceptance of PWR nuclear power plant
- NB/T 20431-2017Structural integrity test of steel containment vessel for pressurized water reactor nuclear power plants
- NB/T 20450.5-2017Alternative welding code for mechanical components of PWR nuclear islands - Part 5: Examination of production welds
Similar standards
Editions of NB/T 20003.8
| Edition | Title | Revision | Status |
|---|---|---|---|
| NB/T 20003.8-2021 | Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 8: Leak testing | current edition | Current |
| NB/T 20003.8-2010 | Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 8: Leak testing | previous edition | Superseded |
This page sells the current edition, NB/T 20003.8-2021. Earlier editions are listed for reference only.
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Related Standards
NB/T 20003.7-2021 — Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 7: Visual testing
NB/T 20003.6-2021 — Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 6: Eddy current testing of tubular products
NB/T 20003.5-2021 — Non-destructive testing for mechanical components in nuclear island of nuclear power plants - Part 5: Magnetic particle testing
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