NB/T 20224-2013Specification for design and fabrication of control rod drive mechanism of PWR nuclear power plants (English PDF)
压水堆核电厂控制棒驱动机构设计制造规范
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Issued by
NEA
Level / Type
Industry · Recommended
Issue date
June 8, 2013
Implementation date
October 1, 2013
Scope
NB/T 20224-2013 is the English-translated version of 压水堆核电厂控制棒驱动机构设计制造规范.
NB/T 20224-2013 is the recommended Chinese energy industry standard for the design and fabrication of the control rod drive mechanism of pressurized water reactors at nuclear power plants.
It lays down the basic requirements for the design, the materials, the manufacture and the inspection of that mechanism. It is written for the magnetic jack type stepping control rod drive mechanisms used in pressurized water reactor plants.
It replaces EJ/T 1137-2001, the earlier nuclear industry standard on the same equipment. It quotes GB/T 4334, GB/T 20066, EJ/T 1027 and the parts NB/T 20003.3-2010, NB/T 20003.4-2010 and NB/T 20003.7-2010. Issued on 8 June 2013, it has applied since 1 October 2013.
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Document preview — NB/T 20224-2013
National Standard of the People's Republic of China
- ICS
- 27.120.20
- Replacing
- EJ/T 1137-2001
Issued by: National Energy Administration of the People's Republic of China
Contents
- 2 Normative references
2 Normative references
NB/T 20224-2013 cites the following standards, which apply in full or in part through the references made to them in its clauses.
GB/T 2652
GB/T 2653
GB/T 2654
GB/T 4334
GB/T 16702
GB/T 20066
EJ/T 564
EJ/T 1012
EJ/T 1027
NB/T 20003.3-2010
NB/T 20003.4-2010
NB/T 20003.7-2010
......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 20 pages — is available in the English PDF.
Referenced standards
Normative references
- GB/T 2652Destructive tests on welds in metallic materials - Longitudinal tensile test on weld metal in fusion welded joints
- GB/T 2653Destructive tests on welds in metallic materials - Bend tests
- GB/T 2654Hardness test methods on welded joints
- GB/T 4334Corrosion of metals and alloys - Test methods for intergranular corrosion of austenitic and ferritic-austenitic (duplex) stainless steels
- GB/T 16702Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
- GB/T 20066Steel and iron -- Sampling and preparation of samples for the determination of chemical composition
EJ/T 564 · EJ/T 1012 · EJ/T 1027
Similar standards
Editions of NB/T 20224
| Edition | Title | Revision | Status |
|---|---|---|---|
| NB/T 20224-2013 | Specification for design and fabrication of control rod drive mechanism of PWR nuclear power plants | current edition | Current |
| EJ/T 1137-2001 | Specification for design and fabrication of control rod drive mechanism of PWR nuclear power plants | previous edition | Superseded |
This page sells the current edition, NB/T 20224-2013. Earlier editions are listed for reference only.
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Related Standards
GB/T 16702.1-2025 — Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants — Part 1: General principle
GB/T 16702.2-2025 — Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 2: Class 1 components
GB/T 16702-2019 — Design code for mechanical components in nuclear island of pressurized water reactor nuclear power plants
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NB/T 20224-2013
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