压水堆核电厂阀门 奥氏体不锈钢锻件技术条件检测

EJ/T 1022.5-1996 压水堆核电厂阀门 奥氏体不锈钢锻件技术条件

Specifications for austenitic stainless steel forgings for valves in pressurized water reactor nuclear power plants

NB/T 20010.5-2010 压水堆核电厂阀门.第5部分:奥氏体不锈钢锻件技术条件

本部分规定了压水堆核电厂核安全相关阀门用奥氏体不锈钢承压锻件(以下简称“锻件”)的技术要求。 本部分适用于压水堆核电厂1、2、3级阀门用锻件(阀体、阀盖、阀瓣等)。核用非核级阀门用锻件也可参照使用。 本部分不适用于阀杆和紧固件

PWR nuclear power plant valve-Part 5: Specification of austenitic stainless steel forging

NB/T 20007.40-2015 压水堆核电厂用不锈钢 第40部分:堆内构件用奥氏体不锈钢锻件

本部分规定了压水堆核电厂堆内构件用奥氏体不锈钢锻件的制造、检验和验收等要求。 本部分适用于压水堆核电厂堆内构件用05Cr19Ni10、06Cr19Ni10奥氏体不锈钢锻件

Stainless steel for pressurized water reactor nuclear power plants.Part 40: austenitic stainless steel forgings used for reactor vessel internals

EJ/T 468-1999 压水堆核电厂不锈钢锻件技术条件

Specification for stainless steel forging for pressurized water reactor nuclear power plants

EJ 467-1989 三十万千瓦压水堆核电厂 奥氏体不锈钢铸件技术条件

Technical Specifications for Austenitic Stainless Steel Castings for 300MW Pressurized Water Reactor Nuclear Power Plant

EJ/T 465-1999 压水堆核电厂马氏体时效不锈钢锻棒技术条件

Specification for martensitic age-stainless steel forging rods for pressurized water reactor nuclear power plants

EJ/T 1022.3-1996 压水堆核电厂阀门 不锈耐酸钢铸件技术条件

Technical specifications for stainless acid-resistant steel castings for pressurized water reactor nuclear power plant valves

EJ/T 486-1999 压水堆核电厂超低碳Cr-Ni奥氏体不锈钢堆焊材料技术条件

Specification for super-low carbon chromium-nickel austenitic stainless steel cladding material for pressurized water reactor nuclear power plants

NB/T 20010.3-2010 压水堆核电厂阀门.第3部分:不锈钢铸件技术条件

本标准规定了压水堆核电厂与核安全相关阀门用不锈钢承压铸件(以下简称“铸件”)的技术要求。 本标准适用于压水堆核电厂1、2、3级阀门用铸件(阀体、阀盖、阀瓣等

PWR nuclear power plant valve-Part 3: Specification of stainless steel casting

NB/T 20007.1-2010 压水堆核电厂用不锈钢.第1部分:1、2、3级奥氏体不锈钢锻件

本部分规定了压水堆核电厂l、2、3级设备用06Crl9Nil0、022Crl9Nil0、026Crl9Ni1ON、 06Crl7Nil2Mo2、022Crl7Nil2Mo2、026Crl8Nil2Mo2N、06Crl8NillTi奥氏体不锈钢锻件的制造、化学成分、力学性能和验收等要求。 本部分

Stainless steel for pressurized water reactor nuclear power plants-Part 1: Class 1,2 and 3 austenitic stainless steel forgings

EJ 465-1989 三十万千瓦压水堆核电厂 马氏体不锈钢锻棒技术条件

Technical conditions for martensitic stainless steel forged rods for 300,000-kilowatt pressurized water reactor nuclear power plants

NB/T 20007.1-2021 压水堆核电厂用不锈钢 第1部分：1、2、3级奥氏体不锈钢锻件

Stainless Steel for Pressurized Water Reactor Nuclear Power Plant Part 1: Forgings of Grade 1, 2, and 3 Austenitic Stainless Steel

NB/T 20007.50-2018 压水堆核电厂用不锈钢 第50部分：安全级设备用奥氏体不锈钢锻件

Stainless steel for use in pressurized water reactor nuclear power plants Part 50: Austenitic stainless steel forgings for safety grade equipment

NB/T 20007.6-2012 压水堆核电厂用不锈钢.第6部分：堆内构件用控氮奥氏体不锈钢板

本部分规定了压水堆核电厂反应堆堆内构件用026Cr19Ni10N控氮奥氏体不锈钢板的制造、化学成分、力学性能、试验方法、检验规则等技术要求。 本部分适用于压水堆核电厂反应堆堆内构件用厚度为10mm～100mm的026Cr19Ni10N控氮奥氏体不锈钢板

Stainless steel for pressurized water reactor nuclear power plants.Part 6:Controlled nitrogen content anstenitic stainless steel plate for Reactor Internal

EJ 468-1989 三十万千瓦压水堆核电厂 0Cr18Ni11Ti不锈钢锻件技术条件

Technical conditions for 0Cr18Ni11Ti stainless steel forgings for 300,000-kilowatt pressurized water reactor nuclear power plant

EJ/T 1022.5-1996 压水堆核电厂阀门 奥氏体不锈钢锻件技术条件

Specifications for austenitic stainless steel forgings for valves in pressurized water reactor nuclear power plants

NB/T 20010.5-2010 压水堆核电厂阀门.第5部分:奥氏体不锈钢锻件技术条件

本部分规定了压水堆核电厂核安全相关阀门用奥氏体不锈钢承压锻件(以下简称“锻件”)的技术要求。 本部分适用于压水堆核电厂1、2、3级阀门用锻件(阀体、阀盖、阀瓣等)。核用非核级阀门用锻件也可参照使用。 本部分不适用于阀杆和紧固件

PWR nuclear power plant valve-Part 5: Specification of austenitic stainless steel forging

NB/T 20007.40-2015 压水堆核电厂用不锈钢 第40部分:堆内构件用奥氏体不锈钢锻件

本部分规定了压水堆核电厂堆内构件用奥氏体不锈钢锻件的制造、检验和验收等要求。 本部分适用于压水堆核电厂堆内构件用05Cr19Ni10、06Cr19Ni10奥氏体不锈钢锻件

Stainless steel for pressurized water reactor nuclear power plants.Part 40: austenitic stainless steel forgings used for reactor vessel internals

EJ/T 468-1999 压水堆核电厂不锈钢锻件技术条件

Specification for stainless steel forging for pressurized water reactor nuclear power plants

EJ 467-1989 三十万千瓦压水堆核电厂 奥氏体不锈钢铸件技术条件

Technical Specifications for Austenitic Stainless Steel Castings for 300MW Pressurized Water Reactor Nuclear Power Plant

EJ/T 465-1999 压水堆核电厂马氏体时效不锈钢锻棒技术条件

Specification for martensitic age-stainless steel forging rods for pressurized water reactor nuclear power plants

EJ/T 1022.3-1996 压水堆核电厂阀门 不锈耐酸钢铸件技术条件

Technical specifications for stainless acid-resistant steel castings for pressurized water reactor nuclear power plant valves

EJ/T 486-1999 压水堆核电厂超低碳Cr-Ni奥氏体不锈钢堆焊材料技术条件

Specification for super-low carbon chromium-nickel austenitic stainless steel cladding material for pressurized water reactor nuclear power plants

NB/T 20010.3-2010 压水堆核电厂阀门.第3部分:不锈钢铸件技术条件

本标准规定了压水堆核电厂与核安全相关阀门用不锈钢承压铸件(以下简称“铸件”)的技术要求。 本标准适用于压水堆核电厂1、2、3级阀门用铸件(阀体、阀盖、阀瓣等

PWR nuclear power plant valve-Part 3: Specification of stainless steel casting

NB/T 20007.1-2010 压水堆核电厂用不锈钢.第1部分:1、2、3级奥氏体不锈钢锻件

本部分规定了压水堆核电厂l、2、3级设备用06Crl9Nil0、022Crl9Nil0、026Crl9Ni1ON、 06Crl7Nil2Mo2、022Crl7Nil2Mo2、026Crl8Nil2Mo2N、06Crl8NillTi奥氏体不锈钢锻件的制造、化学成分、力学性能和验收等要求。 本部分

Stainless steel for pressurized water reactor nuclear power plants-Part 1: Class 1,2 and 3 austenitic stainless steel forgings

EJ 465-1989 三十万千瓦压水堆核电厂 马氏体不锈钢锻棒技术条件

Technical conditions for martensitic stainless steel forged rods for 300,000-kilowatt pressurized water reactor nuclear power plants

NB/T 20007.1-2021 压水堆核电厂用不锈钢 第1部分：1、2、3级奥氏体不锈钢锻件

Stainless Steel for Pressurized Water Reactor Nuclear Power Plant Part 1: Forgings of Grade 1, 2, and 3 Austenitic Stainless Steel

NB/T 20007.50-2018 压水堆核电厂用不锈钢 第50部分：安全级设备用奥氏体不锈钢锻件

Stainless steel for use in pressurized water reactor nuclear power plants Part 50: Austenitic stainless steel forgings for safety grade equipment

NB/T 20007.6-2012 压水堆核电厂用不锈钢.第6部分：堆内构件用控氮奥氏体不锈钢板

本部分规定了压水堆核电厂反应堆堆内构件用026Cr19Ni10N控氮奥氏体不锈钢板的制造、化学成分、力学性能、试验方法、检验规则等技术要求。 本部分适用于压水堆核电厂反应堆堆内构件用厚度为10mm～100mm的026Cr19Ni10N控氮奥氏体不锈钢板

Stainless steel for pressurized water reactor nuclear power plants.Part 6:Controlled nitrogen content anstenitic stainless steel plate for Reactor Internal

EJ 468-1989 三十万千瓦压水堆核电厂 0Cr18Ni11Ti不锈钢锻件技术条件

Technical conditions for 0Cr18Ni11Ti stainless steel forgings for 300,000-kilowatt pressurized water reactor nuclear power plant