Filter :
| Standard and/or project | Stage | TC |
|---|---|---|
|
ISO 7753:1987 [Withdrawn]
Nuclear energy — Performance and testing requirements for criticality detection and alarm systems
|
95.99 | ISO/TC 85/SC 5 |
|
ISO 10270:1995 [Withdrawn]
Corrosion of metals and alloys — Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
|
95.99 | ISO/TC 156 |
|
ISO 10270:1995/Cor 1:1997 [Withdrawn]
Corrosion of metals and alloys — Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors — Technical Corrigendum 1
|
95.99 | ISO/TC 156 |
|
Corrosion of metals and alloys — Aqueous corrosion testing of zirconium alloys for use in nuclear power reactors
|
60.60 | ISO/TC 156 |
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ISO 10645:1992 [Withdrawn]
Nuclear energy — Light water reactors — Calculation of the decay heat power in nuclear fuels
|
95.99 | ISO/TC 85/SC 6 |
|
Nuclear energy — Light water reactors — Decay heat power in non-recycled nuclear fuels
|
60.60 | ISO/TC 85/SC 6 |
|
ISO 10979:1994 [Withdrawn]
Identification of fuel assemblies for nuclear power reactors
|
95.99 | ISO/TC 85/SC 6 |
|
Identification of fuel assemblies for nuclear power reactors
|
90.92 | ISO/TC 85/SC 6 |
|
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
|
50.00 | ISO/TC 85/SC 6 |
|
Steady-state neutronics methods for power-reactor analysis
|
90.92 | ISO/TC 85/SC 6 |
|
ISO/FDIS 18075 [Under development]
Reactor technology — Power reactor analysis — Steady-state neutronics methods
|
50.20 | ISO/TC 85/SC 6 |
|
ISO 18077:2018 [Withdrawn]
Reload startup physics tests for pressurized water reactors
|
95.99 | ISO/TC 85/SC 6 |
|
Reload startup physics tests for pressurized water reactors
|
60.60 | ISO/TC 85/SC 6 |
|
Essential technical requirements for mechanical components and metallic structures foreseen for Generation IV nuclear reactors
|
90.93 | ISO/TC 85/SC 6 |
|
Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
|
90.92 | ISO/TC 85/SC 6 |
|
ISO/DIS 19226 [Under development]
Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
|
40.99 | ISO/TC 85/SC 6 |
|
ISO/DIS 19696 [Under development]
Fusion technology — Magnetic confinement fusion — Test methods for low temperature mechanical properties of electrical insulation materials of superconducting magnets
|
40.00 | ISO/TC 85/SC 6 |
|
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 1: Mechanized ultrasonic testing
|
90.93 | ISO/TC 85/SC 6 |
|
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 2: Magnetic particle and penetrant testing
|
90.93 | ISO/TC 85/SC 6 |
|
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 3: Hydrostatic testing
|
90.93 | ISO/TC 85/SC 6 |
|
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 4: Visual testing
|
90.93 | ISO/TC 85/SC 6 |
|
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/TC 85/SC 6 |
|
ISO/DIS 22996 [Under development]
Reactor technology — Fission research reactor — Design and operation
|
40.00 | ISO/TC 85/SC 6 |
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ISO/DIS 23010 [Under development]
Reactor technology — Fission research reactor — Waste and decommissioning
|
40.00 | ISO/TC 85/SC 6 |
|
Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors
|
60.60 | ISO/TC 85/SC 6 |
|
Reactor technology — Power reactor analyses and measurements — Determination of heavy water isotopic purity by Fourier transform infrared spectroscopy
|
60.60 | ISO/TC 85/SC 6 |
|
Nuclear facilities — Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
|
90.60 | ISO/TC 85/SC 2 |
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