ZH
KR
JP
ES
RU
DEheap
heap, Total:500 items.
In the international standard classification, heap involves: Wastes, Conducting materials, Nuclear energy engineering, Environmental protection, Measurement of volume, mass, density, viscosity, Transformers. Reactors, Welding, brazing and soldering, Air quality, Products of the textile industry, Fertilizers, Rubber and plastics products, Agricultural machines, implements and equipment, Rectifiers. Convertors. Stabilized power supply, Industrial trucks, Woodworking equipment, Iron and steel products, Thermodynamics and temperature measurements, Adhesives, Freight distribution of goods, Farm buildings, structures and installations, Food products in general, Plastics, Radiation measurements, Lifting equipment, Transport, Storage equipment, Items of art and handicrafts, Applications of information technology, Construction materials, Furniture, Electromagnetic compatibility (EMC), Equipment for the metallurgical industry, Geology. Meteorology. Hydrology, Fluid power systems, Continuous handling equipment, Linear and angular measurements, Fuels, Protection against dangerous goods, Products of the chemical industry, Metalliferous minerals, Graphic technology, Vocabularies, Pesticides and other agrochemicals, Chipless working equipment, Water quality, Ferrous metals, Power stations in general, Analytical chemistry, MATERIALS HANDLING EQUIPMENT, Farming and forestry, Materials for the reinforcement of composites, Test conditions and procedures in general, Power transmission and distribution networks, Measurement of force, weight and pressure, Plant and equipment for the food industry, Cutting tools.
Professional Standard - Urban Construction, heap
Professional Standard - Nuclear Industry, heap
- EJ/T 561-1991 PWR Shutdown Cooling Guidelines
- EJ/T 318-1992 Reactor Design Criteria 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 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 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 503-1990 300MW Pressurized Water Reactor Nuclear Power Plant Reactor Internals Design and Manufacturing Specifications
- 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 493-1989 300MW PWR Nuclear Power Plant Reactor Core Neutron Flux Measurement System Piping Design Regulations
- 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/T 20101-2016 Design criteria for sodium cooled fast breeder reactor.Core support structures design
- 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 1176-2005 Management of research reactor ageing
- EJ/T 720-2008 Design criterion for the thermal insulation of reactor vessel and reactor coolant pipings and equipments of PWR nuclear power plants
- EJ/T 720-1992 Design criteria for the insulation layer of reactor pressure vessels and reactor coolant system piping and equipment in 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 1238-2014 Physics and thermal design requirements for reactor fuel assembly irradiation test
- EJ/T 20044-2014 Design criteria for sodium cooled fast breeder reactor.General design of reactor structure
- EJ/T 779-1993 Predicted transient analysis requirements for PWR nuclear power plants that fail to emergency shut down
- EJ/T 20206-2018 Sodium Cooled Fast Breeder Reactor Design Criteria Reactor Overpressure Protection System
- EJ/T 474-2000 Specification for reactor pressure vessel metal insulation for pressurized water reactor nuclear power plants
- EJ/T 1027.9-1996 Welding code for mechanical components of PWR nuclear islands Hardfacing on Valve
- 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 567-1991 Nuclear Reactor Instrumentation Terminology
- 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
- EJ/T 1027.8-1996 Welding code for mechanical components of PWR nuclear islands Anticorrosion overlaying with nickel - base alloy
- EJ/T 712-1992 Technical requirements for the installation of reactor pressure vessels and related equipment in pressurized water reactor nuclear power plants
- EJ 334-1988 Design criteria for main equipment supports of reactor coolant system in pressurized water reactor nuclear power plant
- EJ/T 603-2005 Criteria for safety systems of research reactors
- EJ/T 876-1994 Production stack decommissioning quality assurance
- EJ 622-1992 Reactor Fuel Element Terminology
- EJ/T 836-1994 Pulse Reactor Commissioning Program
- EJ/T 675-1992 Fission ionization chamber for reactor
- EJ/T 486-1999 Specification for super-low carbon chromium-nickel austenitic stainless steel cladding material for pressurized water reactor nuclear power plants
- EJ/T 383-1989 Transient regulations for design of reactor coolant system in 300 MW pressurized water reactor nuclear power plant
- EJ/T 918-1994 Guidelines for the formulation of pressure-temperature limit curves for reactor pressure vessels in pressurized water reactor nuclear power plants
- EJ/T 1027.7-1996 Welding code for mechanical components of PWR nuclear islands Anticorrosion overlaging with austenitic stainless steel
- EJ/T 1027.16-1996 Welding code for mechanical components of PWR nuclear islands Hardfacing procedure qualification on valve
- EJ/T 483-1989 Guidelines for Preparation of Technical Documentation for Reactor Pressure Vessels of 300MW Pressurized Water Reactor Nuclear Power Plant
- EJ/T 384-1989 300MW Pressurized Water Reactor Nuclear Power Plant Reactor Coolant Main Piping Installation Technical Conditions
- EJ/T 668-1992 Design criteria for reactor coolant pressure boundary leak detection system for pressurized water reactor nuclear power plants
- EJ 310-1988 PWR Nuclear Power Plant Engineering Terminology
IAEA - International Atomic Energy Agency, heap
工业和信息化部, heap
HU-MSZT, heap
US-FCR, heap
Professional Standard - Energy, heap
- NB/T 20435-2017RK PWR Nuclear Power Plant Reactor Commissioning Start-up Core Physical Test
- 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 20057.3-2012 PWR nuclear power plants reactor system design.Core.Part3:Fuel assembly
- NB/T 20556-2019 Calculation Method of Excess Reactivity in Heavy Water Reactor Core
- NB/T 20057.4-2012 PWR nuclear power plants reactor system design.Core.Part4:Core components
- NB/T 20382-2016 Vibration monitoring of internal structures in pressurized water reactor nuclear power plants
- NB/T 20144-2012 Initial criticality tests for pressurized water reactor of 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 20434-2017RK PWR Nuclear Power Plant Reactor's First Fuel Loading Test
- NB/T 20592-2021 Flow-induced vibration test of PWR internal components model
- NB/T 20057.2-2012 Pressurized water reactor nuclear power plants reactor system design.Core.Part 2: Thermal hydraulic design criteria
- NB/T 20285-2014 General requirements of reactor system design for 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 20006.36-2017 Alloy steel for pressurized water reactor nuclear power plants.Part 36: 19MnNiMo steel forgings for reactor vessel core region
- 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 20006.37-2017 Alloy steel for pressurized water reactor nuclear power plants.Part 37: 19MnNiMo steel forgings for reactor vessel non-core region
- 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/T 20115-2012 Technical regulation for construction and acceptance of reactor pressure vessel head installation in PWR nuclear power plant
- 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 20044-2011 Technical regulation for construction and acceptance of reactor internals installation in PWR nuclear power plant
- NB/T 20107-2012 Technical regulation for construction of reactor coolant pump installation in PWR nuclear power plant
- NB/T 20112-2012 Technical regulation of the cable terminal connection in the reactor building for 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 20569-2019 Commissioning guidelines for passive core cooling system in pressurized water reactor nuclear power plants
- 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 20334-2015 General requirements for noise analysis of reactor and primary loop in pressurized water reactor nuclear power plant
- NB/T 20104-2012 Analysis requirement for anticipated transient without scram on pressurized water reactor nuclear power plants
- NB/T 20343-2015 Design and fabrication specification for the thermal insulation of reactor vessel and reactor coolant pipings and equipments of PWR nuclear power plants
- NB/T 20343-2021 Code for design and manufacture of reactor pressure vessel and reactor coolant system piping and equipment insulation layer in pressurized water reactor nuclear power plant
- 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 20006.38-2017 Alloy steel for pressurized water reactor nuclear power plants.Part 38 19MnNiMo steel forgings for core make-up tank
- NB/T 20159-2012 The construction technical specification for liner of reactor building of PWR nuclear power plant
- 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 20022-2010 The hoisting technical specification for dome of reactor building of PWR nuclear power plant
- NB/T 20002.7-2013 Welding code for mechanical components of PWR nuclear island.Part 7: Hardfacing
- NB/T 20560.7-2021 Filter Design and Performance Evaluation for Emergency Core Cooling System of Pressurized Water Reactor Nuclear Power Plant Part 7: Technical Requirements for Downstream Effects (In-Core) Test
- 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 20392-2016 Technical regulation for construction and acceptance of reactor vessel installation in passive PWR nuclear power plant
- NB/T 20100-2012 Principles for main primary system and main steam system overpressure analysis of pressurized water reactor nuclear power plants
- NB/T 20100-2016 Requirements of overpressure analysis for reactor coolant system and main steam system for pressurized water reactor nuclear power plants
- 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 20009.13-2021 Welding consumables for pressurized water reactor nuclear power plants - Part 13: Welding strips and fluxes for stainless steel surfacing
- NB/T 20100-2016RK Requirements for overpressure analysis of reactor coolant system and main steam system in pressurized water reactor nuclear power plant
- 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 20035-2011 Categorization of conditions of PWR nuclear power plants
- 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 20346-2015 The technical specification of fabrication and assemble for polar crane beam in PWR nuclear power plants
- NB/T 20009.12-2021 Welding consumables for pressurized water reactor nuclear power plants - Part 12: Welding strips and fluxes for nickel-based alloy surfacing
国家能源局, heap
- NB/T 20435-2017 Pressurized water reactor nuclear power plant reactor commissioning starts core physical test
- NB/T 20430-2017 Technical regulations for the installation of reactor top structures in passive dynamic pressurized water reactor nuclear power plants
- NB/T 20524-2018 Design criteria for safe shutdown of pressurized water reactor nuclear power plants
- NB/T 20434-2017 First charging test of pressurized water reactor nuclear power plant reactor
- NB/T 20407-2017 Specifications for design and manufacturing of internal components of pressurized water reactor nuclear power plants
- NB/T 20467-2017 Technical Guidelines for Commissioning of Reactor Protection Systems of Pressurized Water Reactor Nuclear Power Plants
- NB/T 20400-2017 Technical regulations for manufacturing stainless steel components in reactor cavity pools and spent fuel pools in 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 20440-2017 Assessment criteria for rapid fracture prevention of reactor pressure vessels in pressurized water reactor nuclear power plants
- NB/T 20006.39-2017 Alloy steel for pressurized water reactor nuclear power plants Part 39: Steel rods for integrated reactor top components
- NB/T 20006.40-2018 Alloy steel for pressurized water reactor nuclear power plants Part 40: Forgings for integrated reactor top components
- NB/T 20439-2017 Guidelines for developing pressure-temperature limit curves for reactor pressure vessels in pressurized water reactor nuclear power plants
- 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 20574-2019 Pressurized Water Reactor Nuclear Power Plant Commissioning Terminology
Professional Standard - Machinery, heap
ANS - American Nuclear Society, heap
- 58.6-1996 Criteria for Remote Shutdown for Light Water Reactors
- 15.15-1978 Criteria for the Reactor Safety Systems of Research Reactors
- 58.6-1983 CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
- 15.10-1994 Decommissioning of Research Reactors
- 15.16-2015 Emergency Planning for Research Reactors
- 15.16-2008 Emergency planning for research reactors
- 15.7-1977 Research Reactor Site Evaluation
- 15.16-1982 Emergency planning for research reactors
- 15.10-1981 DECOMMISSIONING OF RESEARCH REACTORS (R 1987)
- 15.17-1981 Fire protection program cCriteria for research reactors
- 51.10-1991 Auxiliary Feedwater System for Pressurized Water Reactors
- 14.1-1975 Operation of Fast Pulse Reactors
- 14.1-2004 Operation of Fast Pulse Reactors
- 15.1-1990 Development of technical specifications for research reactors
- 15.1-2007 The development of technical specifications for research reactors
- 15.11-1977 RADIOLOGICAL CONTROL AT RESEARCH REACTOR FACILITIES
- 15.11-2016 Radiation Protection at Research Reactor Facilities
- 15.1-1982 DEVELOPMENT OF TECHNICAL SPECIFICATIONS FOR RESEARCH REACTORS
- 15.11-1993 Radiation Protection at Research Reactor Facilities
- 15.11-2009 radiation protection at research reactor facilities
- 58.11-1983 COOLDOWN CRITERIA FOR LIGHT WATER REACTORS
Korean Agency for Technology and Standards (KATS), heap
CZ-CSN, heap
American Society for Testing and Materials (ASTM), heap
- ASTM UOP563-14 Packed Apparent Bulk Density of Molecular Sieves
- ASTM E706-01 Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)
- ASTM E706-87(1994) Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards, E706(0)
- ASTM E706-23 Red Standard Master Matrix for Light-Water Reactor Pressure Vessel Surveillance Standards (Standard + Redline PDF Bundle)
- ASTM D6009-96(2006) Standard Guide for Sampling Waste Piles
- ASTM D6009-96(2001) Standard Guide for Sampling Waste Piles
- ASTM D6009-12 Standard Guide for Sampling Waste Piles
- ASTM E636-95 Standard Guide for Conducting Supplemental Surveillance Tests for Nuclear Power Reactor Vessels, E706 (IH)
- ASTM D6009-96 Standard Guide for Sampling Waste Piles
- ASTM D6825-02 Standard Guide for Placement of Riprap Revetments
- ASTM D6825-02e2 Standard Guide for Placement of Riprap Revetments
- ASTM D6825-02e1 Standard Guide for Placement of Riprap Revetments
- ASTM D6400-99e1 Standard Specification for Compostable Plastics
- ASTM D6400-21 Standard Specification for Compostable Plastics
- ASTM D6009-19 Standard Guide for Sampling Waste Piles
GOSTR, heap
- GOST R 57898-2017 Induction-metallurgical method of surfacing. Materials for surfacing
- GOST R 59106-2020 Piled steel screws. Specifications
- GOST R 59023.3-2020 Welding and surfacing of equipment and pipelines of nuclear power plants. Modes of welding and surfacing
- GOST 18624-1973 Reactors. Terms and definitions
- GOST R 59023.6-2020 Welding and surfacing of equipment and pipelines of nuclear power plants. Surfacing of sealing and guiding surfaces
- GOST R 59023.4-2020 Welding and surfacing of equipment and pipelines of nuclear power plants. Requirements for heating during welding (surfacing)
Universal Oil Products Company (UOP), heap
- UOP 563-2014 Packed Apparent Bulk Density of Molecular Sieves
- UOP 778-2007 Packed Apparent Bulk Density (ABD) of Extruded Catalyst
British Standards Institution (BSI), heap
- BS EN 60289:1994 Reactors
- BS IEC 62117:2000 Nuclear reactor instrumentation - Pressurized light water reactors (PWR) - Monitoring adequate cooling within the core during cold shutdown
- PAS 100:2018 Specification for composted materials
- BS IEC 62117:1999 Nuclear reactor instrumentation. Pressurized light water reactors (PWR). Monitoring adequate cooling within the core during cold shutdown.
- BS ISO 4233:2023 Reactor technology. Nuclear fusion reactors. Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
- BS ISO 23466:2020 Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
CENELEC - European Committee for Electrotechnical Standardization, heap
General Administration of Quality Supervision, Inspection and Quarantine of the People‘s Republic of China, heap
- GB 7166-1987 Characteristics and test methods of temperature measurement in nuclear power reactor core or reactor main cladding
- GB/T 984-2001 Hardfacing electrodes for shielded metal arc welding
- GB/T 8995-2008 In-core instrumentation for neutron fluence rate measurements in nuclear reactors
- GB 12789.2-1991 Nuclear Reactor Instrumentation Guidelines Part II: Pressurized Water Reactors
- GB/T 41591-2022 Initial criticality tests for pressurized water reactor of nuclear power plants
- GB/T 13632-1992 Measurements for monitoring adequate cooling within the core of pressurized light water reactors
- GB/T 13566.1-2008 Fertilizers.Determination of bulk density.Part 1:Loose density
- GB/T 12789.3-1992 Criteria for nuclear reactor reactor instrumentation Part three. High temperature gas-cooled reactor(HTGR)
- GB 12789.3-1992 Nuclear Reactor Instrumentation Guidelines Part III: High Temperature Gas Cooled Reactors
- GB/T 21468-2008 Pallet stackers and high-lift platform trucks.Stability tests
- GB/T 13632.2-2006 Measurements for monitoring adequate cooling within the core of pressurized light water reactors - Part 2: Instrumentation requirements during cold shutdown
- GB/T 12789.4-1994 Criteria for nuclear reactor instrumentation. Part four: Liquid-metal cooled fast reactors
- GB/T 12789.4-94 Nuclear Reactor Instrumentation Guidelines Part IV: Liquid Metal Cooled Fast Reactors
- GB/T 26945-2023 Container empty container stacker
- GB/T 26945-2011 Empty container handler
- GB 15146.8-1994 Nuclear criticality safety for fissile materials outside reactors-Criticality safety criteria for the handling,storage and transportation of LWR fuel unit outside reactors
- GB/T 16913.3-1997 Methods of dust character test--Part 3: Determination of bulk density--Natural bulk method
- GB/T 21574-2008 Dangerous goods.Stack test method
- GB/T 28206-2011 Specification for compostable plastic
- GB 15146.8-2008 Nuclear criticality safety for fissile materials outside reactors.Part 8:Criticality safety criteria for the handling,storages,and transportation of LWR fuel outside reactors
- GB 50986-2014 Code for design of dry red mud stack
- GB/T 17569-1998 Classification for the items of pressurized water reactor nuclear power plants
- GB/T 13566-1992 Determination of bulk density for fertilizers
- GB/T 17569-2013 Classification for the items of pressurized water reactor nuclear power pants
- GB/T 38514-2020 Test methods for electrodeionization stacks
- GB/T 7166-2015 Characteristics and test methods for in-core and primary coolant circuit temperature sensors in nuclear power plants
AENOR, heap
Building Officials and Code Administrators International(U.S.), heap
U.S. Military Regulations and Norms, heap
Group Standards of the People's Republic of China, heap
Taiwan Provincial Standard of the People's Republic of China, heap
Lithuanian Standards Office , heap
- LST EN 1237-2002 Fertilizers - Determination of bulk density (tapped) (ISO 5311:1992 modified)
AASHTO - American Association of State Highway and Transportation Officials, heap
- MP 10-2003 Standard Specification for Compost Erosion/Sediment Control (Compost Blankets)
- R 52-2010 Standard Practice for Compost for Erosion/Sediment Control (Compost Blankets)
TR-TSE, heap
U.S. Air Force, heap
United States Navy, heap
American Railway Engineering and Maintenance-of-Way Association (AREMA), heap
国家林业局, heap
International Electrotechnical Commission (IEC), heap
- IEC 61343:1996 Nuclear reactor instrumentation - Boiling light water reactors (BWR) - Measurements in the reactor vessel for monitoring adequate cooling within the core
- IEC 61505:1998 Nuclear reactor instrumentation - Boiling water reactors (BWR) - Stability monitoring
- IEC 62118:2000 Nuclear reactor instrumentation - Pressurized water reactor (PWR) of VVER design - Monitoring adequate cooling within the core during shutdown
- IEC 60911:1987 Measurements for monitoring adequate cooling within the core of pressurized light water reactors
- IEC 60568:1977 Incore instrumentation for the measurement of fluence in power reactors
- IEC 60965:1989 Supplementary control points for reactor shutdown without access to the main control room
- IEC 60231D:1975 General principles of nuclear reactor instrumentation
- IEC 60231G:1977 General principles of nuclear reactor instrumentation. Seventh supplement: Liquid-metal cooled fast reactor
- IEC 60231B:1972 General principles of nuclear reactor instrumentation
- IEC 60231C:1974 General principles of nuclear reactor instrumentation
- IEC 60737:1982 In-core temperature or primary envelope temperature measurements in nuclear power reactors. Characteristics and test methods
- IEC 60231:1967 General principles of nuclear reactor instrumentation
- IEC 60557:1982 I E C terminology in the nuclear reactor field
VDE - VDE Verlag GmbH@ Berlin@ Germany, heap
- VDE 0491-4-2001 Kernkraftwerke - Druckwasserreaktoren - Ueberwachung ausreichender Kuehlung des Kerns im abgeschalteten Zustand des Reaktors (IEC 62117:1999)
RU-GOST R, heap
国家市场监督管理总局、中国国家标准化管理委员会, heap
- GB/T 40408-2021 Nuclear grade isostatic graphite for high temperature gas-cooled reactor internals
- GB/T 41140-2021 Analysis criterion for radiation source term of reactor core and spent fuel assembly in PWR nuclear power plant
- GB/T 40740-2021 Welding procedures qualification for overlay welding
- GB/T 17569-2021 Classification for the items of pressurized water reactor nuclear power plants
SE-SIS, heap
- SIS SS IEC 737:1984 Nuclear instrumentation — In-core temperature or primary envelope temperature measurements in nuclear power reactors — Characteristics and test methods
- SIS SS IEC 639:1981 Nuclear instrumentation - Nuclear reactors - Use of the protection system for non-safety purposes
- SIS SS IEC 911:1988 Nuclear instrumentation — Measurements for monitoring adequate cooling within the core of pressurized light water reactors
- SIS SS IEC 568:1981 Nuclear instrumentation - In-core instrumentation for neutron fluence r?te (flux) measurements in power reactors
Standard Association of Australia （SAA）, heap
- AS 4833:2007 Pressure-sensitive labels for stock-paper, stock-plastic and general purpose use
- AS 2758.4:2000 Aggregates and rock for engineering purposes - Aggregate for gabion baskets and wire mattresses
- AS 2359.8:1995 Powered industrial trucks - Pallet stackers and high-lift platform trucks - Stability tests
- AS 3899:2002(R2013) High-grade coal and coke bulk density
- AS 2879.8:2000(R2013) Determination of bulk density of alumina
AT-ON, heap
American Nuclear Society (ANS), heap
RO-ASRO, heap
Japanese Industrial Standards Committee (JISC), heap
American National Standards Institute （ANSI), heap
Anhui Provincial Standard of the People's Republic of China, heap
ES-AENOR, heap
VDI - Verein Deutscher Ingenieure, heap
International Organization for Standardization (ISO), heap
- ISO 4233:2023 Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
- ISO 17088:2021 Specifications for compostable plastics
- ISO 3944:1992 Fertilizers; determination of bulk density (loose)
- ISO 5311:1992 Fertilizers; determination of bulk density (tapped)
- ISO 5525:1986 Potatoes; Storage in the open (in clamps)
- ISO 10979:2019 Identification of fuel assemblies for nuclear power reactors
- ISO 9136:1989 Abrasive macrograins; determination of bulk density
- ISO 23466:2020 Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
Association Francaise de Normalisation, heap
- NF EN IEC 62282-7-2:2021 Technologies des piles à combustible - Partie 7-2 : méthodes d'essai - Essais de performance de cellule élémentaire et de pile pour les piles à combustible à oxyde solide (SOFC)
- NF EN 14700:2022 Produits consommables de soudage - Produits consommables pour le rechargement dur
- 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 U42-403*NF EN 1237:1995 Fertilizers. Determination of bulk density (tapped).
- NF A20-200*NF ISO 3852:1989 Iron ores. Determination of bulk density.
- NF ISO 3852:1989 Minerais de fer - Détermination de la masse volumique apparente
Professional Standard - Light Industry, heap
- QB/T 2672-2004 Define,marking and compostability requirement of compostable plastic sheet
IN-BIS, heap
- IS 13897-1993 In-core instrumentation for neutron fluence rate (flux ) measurements in power reactors
Military Standard of the People's Republic of China-General Armament Department, heap
- GJB 4256-2001 Safety requirements for external nuclear criticality of nuclear submarine reactor fuel elements
- GJB 843.20-1994 Safety regulations for submarine nuclear power plant design and design criteria for pressurized water reactor internals
IT-UNI, heap
- UNI 7549-P4-1976 Light aggregate. Volumetric mass determination of piles of material (pile weight)
American Society of Mechanical Engineers (ASME), heap
ISA - International Society of Automation, heap
Xizang Provincial Standard of the People's Republic of China, heap
The American Road & Transportation Builders Association, heap
- AASHTO R 52-2010 Standard Practice for Compost for Erosion/Sediment Control (Compost Blankets)
未注明发布机构, heap
- NB 20481-2018 Design and manufacturing specifications for reactor coolant main piping in pressurized water reactor nuclear power plants
- NB 20006.40-2018 Alloy steel for pressurized water reactor nuclear power plants Part 40: Forgings for integrated reactor top components
- BS IEC 60965:2009 Nuclear power plants — Control rooms — Supplementary control points for reactor shutdown without access to the main control room
- NB 20490-2018 Monitoring requirements for activated corrosion product deposition source items during shutdown and maintenance of pressurized water reactor nuclear power plants
- GJB 820A-2018 Specification for coatings for submarine reactor compartments
German Institute for Standardization, heap
- DIN IEC 62117:2001 Nuclear power plants - Pressurized light water reactors - Monitoring adequate cooling within the core during cold shutdown (IEC 62117:1999)
- DIN SPEC 35234:2018 Qualification testing of welders - Fusion welding - Overlay welding
- DIN SPEC 35234:2018-07 Qualification testing of welders - Fusion welding - Overlay welding
VN-TCVN, heap
TH-TISI, heap
(U.S.) Joint Electron Device Engineering Council Soild State Technology Association, heap
Professional Standard - Non-ferrous Metal, heap
Defense Logistics Agency, heap
Professional Standard - Ocean, heap
Professional Standard - Traffic, heap
AWS - American Welding Society, heap
- PRGHF-2002 The Practical Reference Guide for Hardfacing
- A5.21-2001 Specification for Bare Electrodes and Rods for Surfacing
Hebei Provincial Standard of the People's Republic of China, heap
Danish Standards Foundation, heap
- DS/EN 60965:2011 Nuclear power plants - Control rooms - Supplementary control points for reactor shutdown without access to the main control room
Professional Standard - Textile, heap
Professional Standard - Electron, heap
- SJ 1943-1981 Detail specification for high voltage silicon rectifier stacks,Type 2CL12~20 and 2DL12~20
中华人民共和国国家质量监督检验检疫总局、中国国家标准化管理委员会, heap
American Welding Society (AWS), heap
Fujian Provincial Standard of the People's Republic of China, heap
Professional Standard - Environmental Protection, heap
- HJ 843-2017 Emergency-Related Parameters for Research Reactors
工业和信息化部/国家能源局, heap
European Committee for Electrotechnical Standardization（CENELEC）, heap
- EN 60965:2011 Nuclear power plants - Control rooms - Supplementary control points for reactor shutdown without access to the main control room
- EN 60965:2016 Nuclear power plants - Control rooms - Supplementary control room for reactor shutdown without access to the main control room
Indonesia Standards, heap
Guangdong Provincial Standard of the People's Republic of China, heap
- DB44/T 361-2006 Control limits against harmful substances in composts for agricultural use
Professional Standard - Electricity, heap
YU-JUS, heap
WRC - Welding Research Council, heap
Shandong Provincial Standard of the People's Republic of China, heap
- DB37/T 3591-2019 Technical specification for livestock and poultry manure composting
Ningxia Provincial Standard of the People's Republic of China, heap
- DB64/T 871-2013 Technical specification for livestock and poultry manure composting
Guangxi Provincial Standard of the People's Republic of China, heap
Shaanxi Provincial Standard of the People's Republic of China, heap
Jilin Provincial Standard of the People's Republic of China, heap
Liaoning Provincial Standard of the People's Republic of China, heap
Chongqing Provincial Standard of the People's Republic of China, heap
Heilongjiang Provincial Standard of the People's Republic of China, heap
石家庄市市场监督管理局, heap
农业农村部, heap
- NY/T 3442-2019 Technical Specifications for Composting of Livestock and Poultry Manure
机械工业部, heap
- JB 7326-1994 Bucket wheel stacker and reclaimer safety regulations
Professional Standard - Railway, heap
Jiangxi Provincial Standard of the People's Republic of China, heap
CH-SNV, heap