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Standard and/or project under the direct responsibility of ISO/TC 85/SC 6 Secretariat | Stage | ICS |
---|---|---|
Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
|
60.60 | |
Design of nuclear power plants against seismic events — Part 1: Principles
|
60.60 | |
Design of nuclear power plants against seismic events — Part 3: Civil structures
|
60.60 | |
Design of nuclear power plants against seismic events — Part 4: Components
|
60.60 | |
Design of nuclear power plants against seismic events — Part 5: Seismic instrumentation
|
60.60 | |
Design of nuclear power plants against seismic events — Part 6: Post-seismic measures
|
60.60 | |
Nuclear power plants — Design against seismic hazards
|
95.99 | |
Nuclear power plants — Reliability data exchange — General guidelines
|
95.99 | |
Nuclear power plants — Guidelines to ensure quality of collected data on reliability
|
95.99 | |
Nuclear power plants — Maintainability — Terminology
|
90.93 | |
Nuclear energy — Light water reactors — Calculation of the decay heat power in nuclear fuels
|
95.99 | |
Nuclear energy — Light water reactors — Decay heat power in non-recycled nuclear fuels
|
60.60 | |
Identification of fuel assemblies for nuclear power reactors
|
95.99 | |
Identification of fuel assemblies for nuclear power reactors
|
90.92 | |
Reactor technology – Nuclear power reactors – Identification of fuel assemblies
|
20.00 |
|
Design and performance evaluation of emergency core cooling system strainer for pressurized water reactor nuclear power plants — Part 1: General principles
|
30.60 |
|
Steady-state neutronics methods for power-reactor analysis
|
90.92 | |
Reactor technology - Power reactor analysis - Steady-state neutronics methods
|
30.60 |
|
Reload startup physics tests for pressurized water reactors
|
95.99 | |
Reload startup physics tests for pressurized water reactors
|
60.60 | |
Method for the justification of fire partitioning in water cooled nuclear power plants (NPP)
|
90.92 | |
Method for the justification of fire partitioning in water cooled nuclear power plants (NPP)
|
20.60 |
|
Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors
|
90.93 | |
Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
|
90.92 | |
Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
|
20.00 |
|
Reactor technology — Magnetic confinement fusion — Test methods for low temperature mechanical properties of electrical insulation materials of superconducting devices
|
20.00 |
|
Reactor technology — Experimental magnetic confinement fusion reactor — Supersonic molecular beam injection fueling technique for nuclear fusion devices
|
20.00 |
|
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 1: Mechanized ultrasonic testing
|
60.60 | |
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 2: Magnetic particle and penetrant testing
|
60.60 | |
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 3: Hydrostatic testing
|
60.60 | |
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 4: Visual testing
|
60.60 | |
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 5: Eddy current testing of steam generator heating tubes
|
60.60 | |
Reactor Technology — Fission Research Reactor — Design and Operation
|
20.00 |
|
Reactor Technology — Technical specifications for Fission Research Reactor — Waste and Decommissioning
|
20.00 |
|
Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors
|
60.60 | |
Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
|
60.60 | |
Ice plug isolation of piping in nuclear power plant
|
60.60 | |
Reactor technology — Power reactor analyses and measurements — Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy
|
60.60 |
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