Filter :
| 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 | |
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Design of nuclear power plants against seismic events — Part 6: Post-seismic measures
|
60.60 | |
|
ISO 6258:1985 [Withdrawn]
Nuclear power plants — Design against seismic hazards
|
95.99 | |
|
ISO 6527:1982 [Withdrawn]
Nuclear power plants — Reliability data exchange — General guidelines
|
95.99 | |
|
ISO 7385:1983 [Withdrawn]
Nuclear power plants — Guidelines to ensure quality of collected data on reliability
|
95.99 | |
|
Nuclear power plants — Maintainability — Terminology
|
90.60 | |
|
ISO 10645:1992 [Withdrawn]
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 | |
|
ISO 10979:1994 [Withdrawn]
Identification of fuel assemblies for nuclear power reactors
|
95.99 | |
|
Identification of fuel assemblies for nuclear power reactors
|
90.92 | |
|
ISO/CD 10979 [Under development]
Reactor technology – Nuclear power reactors – Identification of fuel assemblies
|
30.92 |
|
|
ISO/FDIS 17838-1 [Under development]
Reactor technology — Design and performance evaluation of the emergency core cooling system strainer in pressurized water reactor nuclear power plants — Part 1: General principles
|
50.20 | |
|
Steady-state neutronics methods for power-reactor analysis
|
90.92 | |
|
ISO/FDIS 18075 [Under development]
Reactor technology — Power reactor analysis — Steady-state neutronics methods
|
50.20 | |
|
ISO 18077:2018 [Withdrawn]
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 | |
|
ISO/DIS 18195 [Under development]
Reactor technology – Water cooled nuclear power plants (NPP) - Method for justification of fire partitioning
|
40.20 | |
|
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 | |
|
ISO/DIS 19226 [Under development]
Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
|
40.99 | |
|
ISO/DIS 19696 [Under development]
Fusion technology — Magnetic confinement fusion — Test methods for low temperature mechanical properties of electrical insulation materials of superconducting magnets
|
40.20 | |
|
ISO/FDIS 19991 [Under development]
Fusion technology — Experimental magnetic confinement fusion facilities — Supersonic molecular beam injection fuelling technique for fusion devices
|
50.20 | |
|
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 1: Mechanized ultrasonic testing
|
90.93 | |
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Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 2: Magnetic particle and penetrant testing
|
90.93 | |
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Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 3: Hydrostatic testing
|
90.93 | |
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Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 4: Visual testing
|
90.93 | |
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Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 5: Eddy current testing of steam generator heating tubes
|
90.93 | |
|
ISO/DIS 22996 [Under development]
Reactor technology — Fission research reactor — Design and operation
|
40.20 | |
|
ISO/DIS 23010 [Under development]
Reactor technology — Fission research reactor — Waste and decommissioning
|
40.00 | |
|
Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors
|
60.60 | |
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Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
|
90.60 | |
|
Ice plug isolation of piping in nuclear power plant
|
90.60 | |
|
Reactor technology — Power reactor analyses and measurements — Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy
|
60.60 | |
|
ISO/WD 25852.2 [Under development]
Reactor technology — Nuclear Power Plants — On-site Implementation of Severe Accident Management Guidelines (SAMGs)
|
20.60 |
|
|
ISO/WD 26047 [Under development]
Chemistry control performance indicator for pressurized water reactor nuclear power plant
|
20.60 |
|
|
ISO/AWI 26549 [Under development]
Reactor Technology - Pressurized Water Reactor - Calculation and Calibration Method for Thermal Power
|
20.00 |
|
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