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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
60.00
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
90.60
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
Steady-state neutronics methods for power-reactor analysis
30.20
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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