Filtrar :
Norma o proyecto | Etapa | TC |
---|---|---|
Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors
|
60.60 | ISO/TC 85/SC 6 |
Design of nuclear power plants against seismic events — Part 1: Principles
|
60.60 | ISO/TC 85/SC 6 |
Design of nuclear power plants against seismic events — Part 3: Civil structures
|
60.60 | ISO/TC 85/SC 6 |
Design of nuclear power plants against seismic events — Part 4: Components
|
60.60 | ISO/TC 85/SC 6 |
Design of nuclear power plants against seismic events — Part 5: Seismic instrumentation
|
50.20 | ISO/TC 85/SC 6 |
Design of nuclear power plants against seismic events — Part 6: Post-seismic measures
|
60.60 | ISO/TC 85/SC 6 |
Nuclear power plants — Quality assurance
|
95.99 | ISO/TC 85 |
Nuclear power plants — Design against seismic hazards
|
95.99 | ISO/TC 85/SC 6 |
Nuclear power plants — Reliability data exchange — General guidelines
|
95.99 | ISO/TC 85/SC 6 |
Nuclear power plants — Guidelines to ensure quality of collected data on reliability
|
95.99 | ISO/TC 85/SC 6 |
Nuclear criticality safety — Use of criticality accident alarm systems for operations
|
60.60 | ISO/TC 85/SC 5 |
Nuclear power plants — Maintainability — Terminology
|
90.93 | ISO/TC 85/SC 6 |
Determination of gas porosity and gas permeability of hydraulic binders containing embedded radioactive waste
|
90.60 | ISO/TC 85/SC 5 |
Nuclear fuel technology — Administrative criteria related to nuclear criticality safety
|
90.93 | ISO/TC 85/SC 5 |
Nuclear facilities — Ventilation penetrations for shielded enclosures
|
90.93 | ISO/TC 85/SC 2 |
Nuclear facilities — Ventilation penetrations for shielded enclosures — Amendment 1
|
60.60 | ISO/TC 85/SC 2 |
Nuclear criticality safety — Estimation of the number of fissions of a postulated criticality accident
|
90.93 | ISO/TC 85/SC 5 |
Fusion installations — Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities
|
60.60 | ISO/TC 85/SC 2 |
Nuclear facilities — Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning
|
90.93 | ISO/TC 85/SC 2 |
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 1: General requirements
|
60.60 | ISO/TC 85/SC 2 |
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 2: Radioactive CH3I method
|
30.60 | ISO/TC 85/SC 2 |
Nuclear facilities — Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
|
90.60 | ISO/TC 85/SC 2 |
Method for the justification of fire partitioning in water cooled nuclear power plants (NPP)
|
90.92 | ISO/TC 85/SC 6 |
Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations — Part 1: Sampling of tritium and carbon-14
|
60.60 | ISO/TC 85/SC 2 |
Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations — Part 2: Determination of tritium and carbon-14 activities sampled by bubbling technique
|
40.00 | ISO/TC 85/SC 2 |
Radiation protection — Performance criteria for laboratories performing cytogenetic triage for assessment of mass casualties in radiological or nuclear emergencies — General principles and application to dicentric assay
|
95.99 | ISO/TC 85/SC 2 |
Radiation protection — Performance criteria for laboratories performing initial cytogenetic dose assessment of mass casualties in radiological or nuclear emergencies — General principles and application to dicentric assay
|
60.60 | ISO/TC 85/SC 2 |
(U, Pu)O2 Powders and sintered pellets — Determination of chlorine and fluorine
|
90.93 | ISO/TC 85/SC 5 |
Determination of carbon content of UO2, (U, Gd)O2 and (U, Pu)O2 powders and sintered pellets — Combustion in a high-frequency induction furnace — Infrared absorption spectrometry
|
90.60 | ISO/TC 85/SC 5 |
Nuclear criticality safety — Nuclear criticality safety training for operations
|
60.60 | ISO/TC 85/SC 5 |
Corrosion control engineering life cycle in nuclear power plants — General requirements
|
40.20 | ISO/TC 156/SC 1 |
Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants
|
60.60 | ISO/TC 85/SC 6 |
Ice plug isolation of piping in nuclear power plant
|
60.60 | ISO/TC 85/SC 6 |
Management of radioactive waste from nuclear facilities — Part 1: General principles, objectives and practical approaches
|
60.60 | ISO/TC 85/SC 5 |
Nuclear energy — Nuclear fuel technology — Methodologies for radioactivity characterization of very low-level waste (VLLW) generated by nuclear facilities
|
60.60 | ISO/TC 85/SC 5 |
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