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Standard and/or project under the direct responsibility of ISO/TC 85/SC 6 Secretariat | Stage | ICS |
---|---|---|
Reactor technology — Nuclear Power Plants —Installation of Structural modules |
30.98 | |
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 |
40.99 | |
Design of Nuclear Power Plants against Seismic Events — Part 3: Civil Structures |
40.99 | |
Design of Nuclear Power Plants against Seismic Events — Part 4: Components |
40.99 | |
Design of Nuclear Power Plants against Seismic Events — Part 5: Seismic Instrumentation |
30.60 | |
Design of Nuclear Power Plants against Seismic Events — Part 6: Post-Seismic Measures |
40.99 | |
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 |
60.60 | |
Design and performance evaluation of emergency core cooling system strainer for pressurized water reactor nuclear power plants — Part 1: General principles |
20.00 |
|
Steady-state neutronics methods for power-reactor analysis |
90.92 | |
Steady-state neutronics methods for power-reactor analysis |
20.00 |
|
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) |
60.60 | |
Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors |
90.20 | |
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 |
|
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 | |
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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