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NB/T 20007.45-2017Stainless steel far pressurized water reactpr nuclear power plant. Part 45: 04Cr13Ni5Mo martensitic stainless steel for hold-down spring (English PDF)

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Issued by

National Energy Administration

Level / Type

National · Recommended

Issue date

February 10, 2017

Implementation date

July 1, 2017

Scope

NB/T 20007.45-2017 (Stainless steel far pressurized water reactpr nuclear power plant. Part 45: 04Cr13Ni5Mo martensitic stainless steel for hold-down spring) is available as an English-translated PDF.

NB/T 20007.45-2017 — This standard specifies the manufacture, inspection and acceptance of 04Cr13Ni5Mo martensitic stainless steel forgings for compression elastic rings of pressurized water reactor nuclear power plants.

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Document preview — NB/T 20007.45-2017

National Standard of the People's Republic of China

ICS: 77.140.85
Classification: H 43

Issued by: National Energy Administration

What this standard covers1
Document data2
Standards quoted by this document3

What this standard covers

This standard specifies the manufacture, inspection and acceptance of 04Cr13Ni5Mo martensitic stainless steel forgings for compression elastic rings of pressurized water reactor nuclear power plants. This standard applies to 04Cr13Ni5Mo martensitic stainless steel forgings for compression elastic rings of pressurized water reactor nuclear power plants.

Document data

International classification (ICS): 77.140.85.

Chinese classification (CCS): H43.

Estimated length of the Chinese original: 10,183 words.

Standards quoted by this document

GB/T 223; GB/T 228.1-2010; GB/T 229-2007; GB/T 231.1; GB/T 4338; GB/T 6394; GB/T 10561-2005; GB/T 11170; GB/T 20066; GB/T 20123; NB/T 20328.2; NB/T 20328.4

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This preview omits tables, figures, formulas and parts of the technical clauses. The complete document — 7 pages — is available in the English PDF.

Referenced standards

Cited by

GB/T 16702.6-2025Design specification for mechanical components in nuclear island of pressurized water reactor nuclear power plants - Part 6: Reactor vessel internals

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