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NB/T 20007.40-2015 English PDF

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NB/T 20007.40-2015: Stainless steel for pressurized water reactor nuclear power plants - Part 40: austenitic stainless steel forgings used for reactor vessel internals
Status: Valid
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NB/T 20007.40-2015English229 Add to Cart 3 days [Need to translate] Stainless steel for pressurized water reactor nuclear power plants - Part 40: austenitic stainless steel forgings used for reactor vessel internals Valid NB/T 20007.40-2015

PDF similar to NB/T 20007.40-2015


Standard similar to NB/T 20007.40-2015

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Basic data

Standard ID NB/T 20007.40-2015 (NB/T20007.40-2015)
Description (Translated English) Stainless steel for pressurized water reactor nuclear power plants - Part 40: austenitic stainless steel forgings used for reactor vessel internals
Sector / Industry Energy Industry Standard (Recommended)
Classification of Chinese Standard H43
Classification of International Standard 77.140.85
Word Count Estimation 10,110
Date of Issue 2015-07-01
Date of Implementation 2015-12-01
Quoted Standard GB/T 223; GB/T 228.1-2010; GB/T 4338; GB/T 6394; GB/T 10561-2005; GB/T 11170; GB/T 20066; GB/T 20123; NB/T 20004-2014; NB/T 20328.2-2015; NB/T 20328.4
Regulation (derived from) Energy Administration Announcement 2015 No.4
Issuing agency(ies) National Energy Administration
Summary This standard specifies the fabrication, inspection and acceptance requirements for pressurized water reactor nuclear power plant reactor components with austenitic stainless steel forgings. This standard applies to PWR nuclear power plant reactor components with 05Cr19Ni10, 06Cr19Ni10 austenitic stainless steel forgings.

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