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NB/T 20007.7-2012 English PDF

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NB/T 20007.7-2012: Stainless steel for pressurized water reactor nuclear power plants. Part 7: Austenitic stainless steel plate and strip for Class Si and S2 supports
Status: Valid
Standard IDUSDBUY PDFLead-DaysStandard Title (Description)Status
NB/T 20007.7-2012419 Add to Cart 3 days Stainless steel for pressurized water reactor nuclear power plants. Part 7: Austenitic stainless steel plate and strip for Class Si and S2 supports Valid

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GB/T 19879   GB/T 20564.10   GB/T 20564.1   NB/T 20007.14   NB/T 20007.15   NB/T 20007.10   

Basic data

Standard ID: NB/T 20007.7-2012 (NB/T20007.7-2012)
Description (Translated English): Stainless steel for pressurized water reactor nuclear power plants. Part 7: Austenitic stainless steel plate and strip for Class Si and S2 supports
Sector / Industry: Energy Industry Standard (Recommended)
Classification of Chinese Standard: H46
Classification of International Standard: 77.140.50
Word Count Estimation: 16,151
Quoted Standard: GB/T 222; GB/T 223.3; GB/T 223.5; GB/T 223.11; GB/T 223.16; GB/T 223.18; GB/T 223.19; GB/T 223.25; GB/T 223.28; GB/T 223.36; GB/T 223.58; GB/T 223.60; GB/T 223.61; GB/T 223.62; GB/T 223.63; GB/T 223.64; GB/T 223.67; GB/T 223.68; GB/T 223.72; GB/T 223.85;
Regulation (derived from): National Energy Board Notice No. 2 of 2012; industry standard for filing Notice No. 4 of 2012 (No. 148 overall)
Issuing agency(ies): National Energy Administration
Summary: This standard specifies the technical requirements for the manufacture, chemical composition, mechanical properties, testing, inspection and acceptance of austenitic stainless steel sheet and strip for S1 and S2 of PWR nuclear power plant. This standard applies to pressurized water reactor nuclear power plant S1, S2 grade support with austenitic stainless steel plate and strip and cold rolled steel.
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