Фильтр :
Стандарт и/или проект | Этап | ТК |
---|---|---|
Reactor technology — Nuclear Power Plants —Installation of Structural modules |
30.98 | ISO/TC 85/SC 6 |
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 |
40.99 | ISO/TC 85/SC 6 |
Design of Nuclear Power Plants against Seismic Events — Part 3: Civil Structures |
40.99 | ISO/TC 85/SC 6 |
Design of Nuclear Power Plants against Seismic Events — Part 4: Components |
40.99 | ISO/TC 85/SC 6 |
Design of Nuclear Power Plants against Seismic Events — Part 5: Seismic Instrumentation |
30.60 | ISO/TC 85/SC 6 |
Design of Nuclear Power Plants against Seismic Events — Part 6: Post-Seismic Measures |
40.99 | 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 |
90.93 | 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 |
90.60 | 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 |
Nuclear installations — Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities |
40.60 | ISO/TC 85/SC 2 |
Nuclear facilities — Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning |
90.20 | 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 |
Nuclear facilities — Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors |
90.93 | ISO/TC 85/SC 2 |
Method for the justification of fire partitioning in water cooled nuclear power plants (NPP) |
60.60 | 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 by bubbling method |
30.20 | 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 |
Nuclear Power Plants Corrosion Control Engineering Life Cycle — General Requirements |
30.20 | 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 |
50.20 | ISO/TC 85/SC 5 |
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