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stack, Total:151 items.
In the international standard classification, stack involves: Linear and angular measurements, Applications of information technology, Measurement of force, weight and pressure, Galvanic cells and batteries, Nuclear energy engineering, Railway engineering in general, Fuel cells, Welding, brazing and soldering, Iron and steel products, Plastics, Protection against fire, Electric road vehicles, Transformers. Reactors, Road vehicles in general, Industrial trucks, Electrical wires and cables.
Group Standards of the People's Republic of China, stack
- T/HIS 001-2022 Infrared Thermopile Sensor
- T/CEC 365-2020 Electric Vehicle Flexible Charging Stack
- T/CMIF 116-2020 Thermopile infrared sensor chip
- T/SDAS 187-2020 Fule cell rolling stock-Performance test methods of fuel cell stack
- T/GHDQ 47-2019 Technical conditions of fuel cell stack life test at subzero environment for fuel cell vehicles in frigid regions
- T/SHDSGY 082-2022 Core physical analysis and fuel management software system for PWR nuclear power plant
- T/GHDQ 45-2019 General technical conditions of automotive fuel cell stack subzero character in frigid region
- T/CSAE 276-2022 Fuel cell stack vibration test specification
- T/GHDQ 44-2019 General technical conditions of automotive proton exchange membrane fuel cell stack subzero startup in frigid region
- T/CSAE 183-2021 General performance test methods for fuel cell stacks and fuel cell systems
- T/ZZB 1072-2019 Battery pallet stacking trucks
- T/CEEIA 489-2020 Class 1E cables for fourth generation nuclear power plant with high temperature gas-cooled reactor
Association Francaise de Normalisation, stack
- NF EN ISO 13927:2015 Plastiques - Essai simple pour la détermination du débit calorifique au moyen d'un radiateur conique et d'une sonde à thermopile
- NF T51-831*NF EN ISO 13927:2015 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector
- NF T51-831:2003 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector.
国家能源局, stack
- NB/T 10460-2020 Test method for zinc-nickel flow battery stack
- NB/T 42132-2017 All-vanadium redox flow battery stack testing method
- NB/T 20407-2017 Specifications for design and manufacturing of internal components of pressurized water reactor nuclear power plants
- NB/T 20434-2017 First charging test of pressurized water reactor nuclear power plant reactor
- NB/T 20524-2018 Design criteria for safe shutdown of pressurized water reactor nuclear power plants
- NB/T 20435-2017 Pressurized water reactor nuclear power plant reactor commissioning starts core physical test
- NB/T 10821-2021 Solid oxide fuel cell stack test method
- NB/T 20467-2017 Technical Guidelines for Commissioning of Reactor Protection Systems of Pressurized Water Reactor Nuclear Power Plants
- NB/T 20430-2017 Technical regulations for the installation of reactor top structures in passive dynamic pressurized water reactor nuclear power plants
- NB/T 20481-2018 Design and manufacturing specifications for reactor coolant main piping in pressurized water reactor nuclear power plants
- NB/T 20522-2018 Nuclear power plant core neutron flux measurement refers to casing eddy current testing
- NB/T 20490-2018 Monitoring requirements for activated corrosion product deposition source items during shutdown and maintenance of pressurized water reactor nuclear power plants
- NB/T 20440-2017 Assessment criteria for rapid fracture prevention of reactor pressure vessels in pressurized water reactor nuclear power plants
工业和信息化部, stack
Professional Standard - Energy, stack
- NB/T 11062-2023 Technical conditions for all-vanadium redox flow battery stacks
- NB/T 20382-2016 Vibration monitoring of internal structures in pressurized water reactor nuclear power plants
- NB/T 20195-2012 Reactor thermal power measurement procedure for reactor core in pressurized water nuclear power plant
- NB/T 20552-2019 Supervision of critical boron concentration in core at pressurized water reactor nuclear power plants
- NB/T 20553-2019 Aging management guideline for internal components in pressurized water reactor nuclear power plants
- NB/T 20115-2012 Technical regulation for construction and acceptance of reactor pressure vessel head installation in PWR nuclear power plant
- 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 20112-2012 Technical regulation of the cable terminal connection in the reactor building for PWR nuclear power plant
- NB/T 20144-2012 Initial criticality tests for pressurized water reactor of nuclear power plants
- NB/T 20434-2017RK PWR Nuclear Power Plant Reactor's First Fuel Loading Test
- NB/T 20285-2014 General requirements of reactor system design for pressurized water reactor nuclear power plants
- NB/T 20101-2012 Analysis requirement for rod ejection accidents of pressurized water reactor nuclear power plants
- NB/T 20101-2021 Analysis Requirements for Reactor Bomb Accidents in Pressurized Water Reactor Nuclear Power Plants
- NB/T 20435-2017RK PWR Nuclear Power Plant Reactor Commissioning Start-up Core Physical Test
- NB/T 20161-2012 Installation and commissioning technical guideline for ex-core neutron flux measuring system for pressurized water reactor of nuclear power plants
- NB/T 20161-2021 Technical regulations for installation and testing of external neutron fluence rate measurement system for pressurized water reactor nuclear power plants
- NB/T 20261-2014 Design criteria for emergency core cooling system of pressurized water reactor nuclear power plants
- NB/T 20187-2012 Design criteria for reactor coolant system in pressurized water reactor nuclear power plants
- NB/T 20131-2012 Design criteria for emergency core cooling sump of pressurized water reactors nuclear power plants
- NB/T10821-2021
- NB/T 20269-2014 Design and fabrication specification for reactor coolant pump of pressurized water ractor nuclear power plant
- NB/T 20304-2014 Technical guideline for installation of reactor protection system of pressured water reactor nuclear power plants
- NB/T 20154-2012 Guideline of ageing management for PWR reactor pressure vessels
- NB/T 20107-2012 Technical regulation for construction of reactor coolant pump installation in PWR nuclear power plant
- NB/T 20606-2021 Technical conditions for underwater maintenance of reactor internals in pressurized water reactor nuclear power plants
- NB/T 20057.1-2012 Pressurized water reactor nuclear power plants reactor system design.Core.Part 1: Nuclear design
- NB/T 20064-2012 Installation and test requirement of in-core instrumentation system in pressured water reator nuclear power plant
- NB/T 20099-2012 Analysis demand for loss-of-coolant accident of pressurized water reactor nuclear power plants
- NB/T 20576-2019 Analysis of Neutron Flux Rate of Reactor Pressure Vessel in PWR Nuclear Power Plant
- NB/T 20057.3-2012 PWR nuclear power plants reactor system design.Core.Part3:Fuel assembly
- NB/T 20334-2015 General requirements for noise analysis of reactor and primary loop in pressurized water reactor nuclear power plant
- NB/T 20569-2019 Commissioning guidelines for passive core cooling system in pressurized water reactor nuclear power plants
- NB/T 20398-2017 Construction and inspection specification for reactor building internal structure of PWR nuclear power plant
- NB/T 20372-2016 Technical regulation for installation of control rod drive mechanism in PWR nuclear power plant
- NB/T 20032-2010 Evaluation rule of pressurized thermal shock for reactor pressure vessel of PWR NPP
- NB/T 20173-2012 Requirements for construction and test of polar crane at PWR reactor building
- NB/T 20045-2011 Technical regulation for construction and acceptance of reactor vessel installation in PWR nuclear power plant
- NB/T 20109-2012 Technical specification of neutron flux guide tube installation in reactor building for PWR nuclear power plant
- NB/T 20582-2021 Technical guidelines for commissioning boron and water supply systems for pressurized water reactor nuclear power plants
- NB/T 20057.4-2012 PWR nuclear power plants reactor system design.Core.Part4:Core components
- NB/T 20159-2012 The construction technical specification for liner of reactor building of PWR nuclear power plant
Professional Standard - Nuclear Industry, stack
- 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 318-1992 Reactor Design Criteria for Pressurized Water Reactor Nuclear Power Plants
- EJ/T 494-1999 Specification for reactor internals compression spring-ring forging for pressurized water reactor nuclear power plants
- EJ/T 1113-2000 Initial critical test in PWR nuclear power plant
- EJ/T 1114-2000 Initial loading test for PWR nuclear power plant
- EJ/T 320-1998 General design criteria of reactor for pressurized water reactor nuclear power plants
- EJ/T 561-2000 Design criteria for safe shutdown of pressurized water reactor nuclear power plants
- EJ/T 1115-2000 Physics tests at low power for PWR nuclear power plant
- EJ/T 319-1992 Thermal-hydraulic Design Criteria for Pressurized Water Reactor Nuclear Power Plant
- EJ 320-1988 General Design Guidelines for Reactor Structure of Pressurized Water Reactor Nuclear Power Plant
- EJ/T 322-1994 Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants
- EJ 322-1988 Design criteria for reactor pressure vessels in pressurized water reactor nuclear power plants
- EJ/T 325-1988 Design criteria for reactor coolant system in pressurized water reactor nuclear power plant
- EJ/T 332-1988 Design criteria for emergency core cooling system of pressurized water reactor nuclear power plant
- EJ/T 816-1994 Design criteria for emergency core cooling pits in pressurized water reactor nuclear power plants
- EJ/T 1137-2001 Design Specification for PWR control rod drive mechanism
- EJ 326-1988 Design criteria for reactor coolant auxiliary systems in pressurized water reactor nuclear power plants
- EJ/T 446-1989 300MW PWR nuclear power plant reactor physical start-up test
- EJ/T 474-2000 Specification for reactor pressure vessel metal insulation for pressurized water reactor nuclear power plants
- EJ/T 444-1989 Regulations on Nuclear Design Contents of 300MW Pressurized Water Reactor Nuclear Power Plant
- EJ/T 448-1989 Technical Specifications for Reactor Coolant Pumps of 300MW PWR Nuclear Power Plant
- EJ/T 732-1992 Evaluation criteria for pressurized thermal shock of reactor pressure vessels in pressurized water reactor nuclear power plants
- EJ/T 606-1991 Ultrasonic In-Service Inspection of Reactor Pressure Vessel Welds in PWR Nuclear Power Plants
- EJ/T 478-1989 300,000-kilowatt pressurized water reactor nuclear power plant reactor pressure vessel top cover assembly
- EJ/T 712-2002 Installation requirements of reactor pressure vessel and its related equipment in PWR nuclear power plant
- EJ/T 1033-1996 Assessment criteria for preventing fast rupture of reactor pressure vessel of pressurized water reactor nuclear power plants
- EJ/T 445-1989 Reactor and Power Distribution Abnormal Analysis of 300MW PWR Nuclear Power Plant
General Administration of Quality Supervision, Inspection and Quarantine of the People‘s Republic of China, stack
- GB/T 31035-2014 Test methods for proton exchange membrane fuel cell stack at subzero environment
- GB/T 41583-2022 Method for core damage assessment of nuclear power plant
- GB/T 41591-2022 Initial criticality tests for pressurized water reactor of nuclear power plants
- GB/T 36288-2018 Fuel cell electric vehicles.Safety requirement of fuel cell stack
- GB/T 20042.2-2008 Proton exchange membrane fuel cell.General technical specification of fud cell stacks
- GB/T 42847.2-2023 Reversible mode fuel cell modules for energy storage systems Part 2: Performance test methods for reversible mode proton exchange membrane cells and stacks
Japanese Industrial Standards Committee (JISC), stack
- JIS Z 3322:1996 Materials for stainless steel overlay welding with strip electrode
- JIS C 8832:2008 Performance test for stationary polymer electrolyte fuel cell stack
- JIS C 8831:2008 Safety evaluation test for stationary polymer electrolyte fuel cell stack
国家市场监督管理总局、中国国家标准化管理委员会, stack
- GB/T 41140-2021 Analysis criterion for radiation source term of reactor core and spent fuel assembly in PWR nuclear power plant
Danish Standards Foundation, stack
- DS/EN ISO 13927:2003 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector
British Standards Institution (BSI), stack
- BS EN ISO 13927:2001 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector
- BS EN ISO 13927:2015 Plastics. Simple heat release test using a conical radiant heater and a thermopile detector
- BS EN ISO 13927:2023 Plastics. Simple heat release test using a conical radiant heater and a thermopile detector
- BS EN IEC 62282-7-2:2021 Tracked Changes. Fuel cell technologies. Test methods. Single cell and stack performance tests for solid oxide fuel cells
- 23/30430975 DC BS EN ISO 13927 Plastics. Simple heat release test using a conical radiant heater and a thermopile detector
- 20/30412786 DC BS EN 62282-7-2. Fuel cell technologies. Part 7-2. Test methods. Single cell and stack performance tests for solid oxide fuel cells (SOFC)
American Society for Testing and Materials (ASTM), stack
- ASTM E906-06 Standard Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
- ASTM E906/E906M-10 Standard Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
- ASTM E906-07 Standard Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
- ASTM E906/E906M-14 Standard Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
- ASTM E906-07e1 Standard Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
- ASTM E906-09 Standard Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
- ASTM E906/E906M-21 Standard Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
- ASTM E906/E906M-17 Standard Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
CEN - European Committee for Standardization, stack
- EN ISO 13927:2003 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector
Korean Agency for Technology and Standards (KATS), stack
- KS M ISO 13927:2004 Plastics-Simple heat release test using a conicalradiant heater and a thermopile detector
- KS M ISO 13927-2016(2021) Plastics－Simple heat release test using a conicalradiant heater and a thermopile detector
- KS M ISO 13927:2016 Plastics－Simple heat release test using a conicalradiant heater and a thermopile detector
- KS C IEC TS 62282-7-2:2016 Fuel cell technologies ― Part 7-2: Test methods ― Single cell and stack performance tests for solid oxide fuel cells(SOFC)
- KS C IEC 61468-2006(2021) Nuclear power plants－In-core instrumentation－Characteristics and test methods of self-powered neutron detectors
KR-KS, stack
- KS M ISO 13927-2016 Plastics－Simple heat release test using a conicalradiant heater and a thermopile detector
German Institute for Standardization, stack
- DIN EN ISO 13927:2003 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector (ISO 13927:2001); German version EN ISO 13927:2003
- DIN EN ISO 13927:2015-08 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector (ISO 13927:2015); German version EN ISO 13927:2015 / Note: To be replaced by DIN EN ISO 13927 (2023-02).
- DIN EN ISO 13927:2023-02 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector (ISO/DIS 13927:2022); German and English version prEN ISO 13927:2022 / Note: Date of issue 2023-01-06*Intended as replacement for DIN EN ISO 13927 (2015-08).
- DIN 25433:2016-10 Fuel assembly identification for nuclear power reactors
- DIN EN ISO 13927:2015 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector (ISO 13927:2015); German version EN ISO 13927:2015
Defense Logistics Agency, stack
International Organization for Standardization (ISO), stack
- ISO/PRF 13927:2023 Plastics — Simple heat release test using a conical radiant heater and a thermopile detector
- ISO 13927:2023 Plastics — Simple heat release test using a conical radiant heater and a thermopile detector
ES-UNE, stack
- UNE-EN ISO 13927:2016 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector (ISO 13927:2015)
- UNE-EN IEC 62282-7-2:2021 Fuel cell technologies - Part 7-2: Test methods - Single cell and stack performance tests for solid oxide fuel cells (SOFCs) (Endorsed by Asociación Española de Normalización in September of 2021.)
Lithuanian Standards Office , stack
- LST EN ISO 13927:2004 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector (ISO 13927:2001)
American National Standards Institute （ANSI), stack
- ANSI/ASTM E906:2010 Test Method for Heat and Visible Smoke Release Rates for Materials and Products Using a Thermopile Method
European Committee for Standardization (CEN), stack
- EN ISO 13927:2015 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector
- prEN ISO 13927 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector (ISO/DIS 13927:2022)
- EN ISO 13927:2023 Plastics - Simple heat release test using a conical radiant heater and a thermopile detector (ISO 13927:2023)
未注明发布机构, stack
- NB 20481-2018 Design and manufacturing specifications for reactor coolant main piping in pressurized water reactor nuclear power plants
- NB 20490-2018 Monitoring requirements for activated corrosion product deposition source items during shutdown and maintenance of pressurized water reactor nuclear power plants
IAEA - International Atomic Energy Agency, stack