ZH
RU
ES

Heap Internals+

Heap Internals+, Total:30 items.

In the international standard classification, Heap Internals+ involves: Conducting materials, Nuclear energy engineering, Iron and steel products, Pipeline components and pipelines, Products of non-ferrous metals.

工业和信息化部, Heap Internals+

YB/T 4912-2021 High-temperature gas-cooled reactor charcoal stack internal components

Professional Standard - Nuclear Industry, Heap Internals+

EJ/T 321-1998 Design criterion of reactor internals for pressurized water reactor nuclear power plants
EJ 321-1988 Design criteria for internal components of pressurized water reactor nuclear power plants
EJ/T 1210-2006 Experiment standard for flow-induced vibration of PWR internals model
EJ/T 1188-2005 Vibration monitoring of internal structures in pressurized water reactor of nuclear power plants
EJ/T 494-1999 Specification for reactor internals compression spring-ring forging for pressurized water reactor nuclear power plants
EJ/T 503-1990 300MW Pressurized Water Reactor Nuclear Power Plant Reactor Internals Design and Manufacturing Specifications

Professional Standard - Energy, Heap Internals+

NB/T 20382-2016 Vibration monitoring of internal structures in pressurized water reactor nuclear power plants
NB/T 20592-2021 Flow-induced vibration test of PWR internal components model
NB/T 20553-2019 Aging management guideline for internal components in pressurized water reactor nuclear power plants
NB/T 20044-2011 Technical regulation for construction and acceptance of reactor internals installation in PWR nuclear power plant
NB/T 20044-2021 Technical regulations for installation and acceptance of internal components of pressurized water reactor nuclear power plants
NB/T 20606-2021 Technical conditions for underwater maintenance of reactor internals in pressurized water reactor nuclear power plants
NB/T 20008.24-2015 Other material for pressurized water reactor nuclear power plants.Part 24: GH4145 alloy bars for reactor vessel internals
NB/T 20008.25-2015 Other material for pressurized water reactor nuclear power plants.Part 25: GH4169 alloy wires for reactor vessel internals
NB/T 20007.42-2015 Stainless steel for pressurized water reactor nuclear power plants.Part 42: precipitation-hardening stainless steel bars for reactor vessel internals
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
NB/T 20007.6-2012 Stainless steel for pressurized water reactor nuclear power plants.Part 6:Controlled nitrogen content anstenitic stainless steel plate for Reactor Internal
NB/T 20007.41-2015 Stainless steel for pressurized water reactor nuclear power plants.Part 41: austenitic stainless steel seamless pipes used for reactor vessel internals
NB/T 20007.17-2012 Stainless steel for pressurized water reactor nuclear power plants.Part 17：Martensitic stainless steel forgings used for internal hold down springs
NB/T 20007.17-2021 Stainless steel for pressurized water reactor nuclear power plant - Part 17: Martensitic stainless steel forgings for compression elastic rings of reactor internals
NB/T 20008.10-2012 Other material for pressurized water reactor nuclear power plants.Part 10：Ni-Cr-Fe alloy rolled bars used for internal support pins and bolting
NB/T 20007.15-2012 Stainless steel for pressurized water reactor nuclear power plants.Part 15：Strain hardened hot worked rolled or forged bars made from anstenitic stainless steel used for the fabrication of bolting material for reactor internals

国家能源局, Heap Internals+

NB/T 20407-2017 Specifications for design and manufacturing of internal components of pressurized water reactor nuclear power plants

国家市场监督管理总局、中国国家标准化管理委员会, Heap Internals+

GB/T 40408-2021 Nuclear grade isostatic graphite for high temperature gas-cooled reactor internals

Group Standards of the People's Republic of China, Heap Internals+

T/CNEA 104.5-2021 PWR pressure boundary components—Equipments design and fabrication— Part 5:Reactor internals

Military Standard of the People's Republic of China-General Armament Department, Heap Internals+

GJB 843.20-1994 Safety regulations for submarine nuclear power plant design and design criteria for pressurized water reactor internals
GJB 843.20A-2005 Safety regulations for the design of submarine nuclear power plants - Part 20: Design criteria for pressurized water reactor internals

未注明发布机构, Heap Internals+

GJB 843.20A-2018 Safety regulations for the design of submarine nuclear power plants Part 20: Design criteria for pressurized water reactor internals

General Administration of Quality Supervision, Inspection and Quarantine of the People‘s Republic of China, Heap Internals+

GB/T 43062-2023 Determination of neutron fluence and atomic dislocation number (dpa) of nuclear energy reactor pressure vessels and internal components