NB/T 20407-2017Specification for design and fabrication of reactor vessel internals in pressurized water reactor nuclear power plants (English PDF)
压水堆核电厂堆内构件设计制造规范
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Issued by
NEA
Level / Type
Industry · Recommended
Issue date
February 10, 2017
Implementation date
July 1, 2017
Scope
NB/T 20407-2017 is the English-translated version of 压水堆核电厂堆内构件设计制造规范.
NB/T 20407-2017 is the Chinese energy industry standard for the reactor vessel internals of pressurized water reactor nuclear power plants, and it brings design and fabrication together in a single specification.
Reactor internals are the structures inside the reactor pressure vessel that hold the core in position and direct the flow of coolant, and they rank among the largest nuclear grade stainless steel components in the plant.
The standard is classified F69 and is recommended. It cites GB/T 4334-2008, GB/T 17569, GB/T 19418-2003, NB/T 20001, the seven parts of NB/T 20002, NB/T 20004, and a run of GB/T 223 chemical analysis methods for steel, beginning with GB/T 223.1 and GB/T 223.11. Issued on 10 February 2017, it has applied since 1 July 2017.
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Document preview — NB/T 20407-2017
National Standard of the People's Republic of China
Issued by: National Energy Administration of the People's Republic of China
Contents
- 2 Normative references
2 Normative references
NB/T 20407-2017 cites the following standards, which apply in full or in part through the references made to them in its clauses.
GB/T 4334-2008
GB/T 17569
GB/T 19418-2003
NB/T 20001
NB/T 20002.1
NB/T 20002.2
NB/T 20002.3
NB/T 20002.4
NB/T 20002.5
NB/T 20002.6
NB/T 20002.7
NB/T 20004
GB/T 223.11
GB/T 223.12
GB/T 223.13
GB/T 223.14
GB/T 223.17
GB/T 223.18
GB/T 223.1
......
This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 32 pages — is available in the English PDF.
Referenced standards
Normative references
- GB/T 4334-2008Corrosion of metals and alloys - Test methods for intergranular corrosion of austenitic and ferritic-austenitic (duplex) stainless steels
- GB/T 17569Classification for the items of pressurized water reactor nuclear power plants
- GB/T 19418-2003Arc-welded joints in steel -- Guidance on quality levels for imperfections
- NB/T 20001Manufacturing specifications for nuclear island machinery and equipment in pressurized water reactor nuclear power plants
- NB/T 20002.1Welding code for mechanical components of PWR nuclear islands - Part 1: General requirements
- NB/T 20002.2Welding code for nuclear island mechanical equipment of pressurized water reactor nuclear power plant - Part 2: Acceptance of welding filler materials
GB/T 223.1
Similar standards
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Related Standards
GB/T 17569-2021 — Classification for the items of pressurized water reactor nuclear power plants
GB/T 19418-2003 — Arc-welded joints in steel -- Guidance on quality levels for imperfections
GB/T 223.11-2008 — Iron, steel and alloy -- Determination of chromium content -- Visual titration or potentiometric titration method
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NB/T 20407-2017
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