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Norma o proyecto bajo la responsabilidad directa de ISO/TC 85/SC 6 Secretaría Etapa 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
ISO 6258:1985 [Retirada]
Nuclear power plants — Design against seismic hazards
95.99
ISO 6527:1982 [Retirada]
Nuclear power plants — Reliability data exchange — General guidelines
95.99
ISO 7385:1983 [Retirada]
Nuclear power plants — Guidelines to ensure quality of collected data on reliability
95.99
Nuclear power plants — Maintainability — Terminology
90.60
ISO 10645:1992 [Retirada]
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 [Retirada]
Identification of fuel assemblies for nuclear power reactors
95.99
Identification of fuel assemblies for nuclear power reactors
90.92
ISO/CD 10979 [En desarrollo]
Reactor technology – Nuclear power reactors – Identification of fuel assemblies
30.92
ISO/FDIS 17838-1 [En desarrollo]
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 [En desarrollo]
Reactor technology — Power reactor analysis — Steady-state neutronics methods
50.20
ISO 18077:2018 [Retirada]
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 [En desarrollo]
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 [En desarrollo]
Nuclear energy — Determination of neutron fluence and displacement per atom (dpa) in reactor vessel and internals
40.99
ISO/DIS 19696 [En desarrollo]
Fusion technology — Magnetic confinement fusion — Test methods for low temperature mechanical properties of electrical insulation materials of superconducting magnets
40.20
ISO/FDIS 19991 [En desarrollo]
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
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 2: Magnetic particle and penetrant testing
90.93
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 3: Hydrostatic testing
90.93
Guidelines for in-service inspections for primary coolant circuit components of light water reactors — Part 4: Visual testing
90.93
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 [En desarrollo]
Reactor technology — Fission research reactor — Design and operation
40.20
ISO/DIS 23010 [En desarrollo]
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
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 [En desarrollo]
Reactor technology — Nuclear Power Plants — On-site Implementation of Severe Accident Management Guidelines (SAMGs)
20.60
ISO/WD 26047 [En desarrollo]
Chemistry control performance indicator for pressurized water reactor nuclear power plant
20.60
ISO/AWI 26549 [En desarrollo]
Reactor Technology - Pressurized Water Reactor - Calculation and Calibration Method for Thermal Power
20.00

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