NB/T 20007.14-2010
Stainless steel for pressurized water reactor nuclear power plants-Part 14: Class 1,2，3 austenitic stainless steel forged or rolled bars (English Version)

Standard No.

NB/T 20007.14-2010

Language

Chinese, Available in English version

Release Date

2010

Published By

Professional Standard - Energy

Status

Be replaced 2021-07

Replace By

NB/T 20007.14-2021

Latest

NB/T 20007.14-2021

Replace

EJ/T 409-1999

Scope

This part specifies the requirements for the manufacturing, chemical composition, mechanical properties and acceptance of austenitic stainless steel forged and rolled rods for Level 1, 2 and 3 equipment in pressurized water reactor nuclear power plants. This section applies to 06Crl9Nil0, 022Crl9Nil0, 026Crl9Nil0N, 06Crl7Nil2Mo2, 022Crl7Nil2Mo2, 026Crl8Nil2Mo2N, 06Crl8NilTi austenitic stainless steel forged and rolled rods for use in level 1, 2 and 3 equipment of pressurized water reactor nuclear power plants.

NB/T 20007.14-2010 history

• 2021 NB/T 20007.14-2021 Stainless steel for pressurized water reactor nuclear power plant Part 14: Grade 1, 2, 3 austenitic stainless steel forging and rolling rods
• 2010 NB/T 20007.14-2010 Stainless steel for pressurized water reactor nuclear power plants-Part 14: Class 1,2，3 austenitic stainless steel forged or rolled bars
• 1970 EJ/T 409-1999 Technical conditions for 0Cr18Ni11Ti stainless steel bars for 300,000-kilowatt pressurized water reactor nuclear power plants

NB/T 20007.14-2010 Stainless steel for pressurized water reactor nuclear power plants-Part 14: Class 1,2，3 austenitic stainless steel forged or rolled bars has been changed from EJ/T 409-1999 Technical conditions for 0Cr18Ni11Ti stainless steel bars for 300,000-kilowatt pressurized water reactor nuclear power plants.