Radiation protection, see 13.280
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Standard and/or project Stage 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
60.60 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
90.93 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
90.93 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
40.20 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
Corrosion control engineering life cycle in nuclear power plants — General requirements
40.60 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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