NB/T 20007.36-2015 English PDF

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NB/T 20007.36-2015: Stainless steel for pressurized water reactor nuclear power plant - Part 36: Austenitic stainless steel forged bars used for pressure-retaining components of CRDM
Status: Valid

Standard ID	USD	BUY PDF	Lead-Days	Standard Title (Description)	Status
NB/T 20007.36-2015	229	Add to Cart	3 days	Stainless steel for pressurized water reactor nuclear power plant - Part 36: Austenitic stainless steel forged bars used for pressure-retaining components of CRDM	Valid

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Basic data

Standard ID: NB/T 20007.36-2015 (NB/T20007.36-2015)
Description (Translated English): Stainless steel for pressurized water reactor nuclear power plant - Part 36: Austenitic stainless steel forged bars used for pressure-retaining components of CRDM
Sector / Industry: Energy Industry Standard (Recommended)
Classification of Chinese Standard: H44
Classification of International Standard: 77.140.60
Word Count Estimation: 10,132
Date of Issue: 2015-04-02
Date of Implementation: 2015-09-01
Quoted Standard: 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 13012 -2008; GB/T 20066; GB/T 20123; GB/T 20124; NB/T 20004-2014; NB/T 20328.2-2015; NB/T 20328.4; ASTM A342/A342M-14
Regulation (derived from): ?Energy Bureau Announcement 2015 No. 3
Issuing agency(ies): National Energy Administration
Summary: This standard specifies the pressurized water reactor nuclear power plant control rod drive mechanism bearing member with 022Cr19Ni10N stainless steel forging bar fabrication, inspection and acceptance requirements. This standard applies to pressurized water reactor nuclear power plant control rod drive mechanism 50 mm larger than the diameter of the bearing member with 022Cr19Ni10N stainless steel forging rods.

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