Reactor technology — Nuclear fusion reactors — Hot helium leak testing method for high temperature pressure-bearing components in nuclear fusion reactors

Design of nuclear power plants against seismic events — Part 1: Principles

Design of nuclear power plants against seismic events — Part 3: Civil structures

Design of nuclear power plants against seismic events — Part 4: Components

Design of nuclear power plants against seismic events — Part 5: Seismic instrumentation

Design of nuclear power plants against seismic events — Part 6: Post-seismic measures

Nuclear power plants — Quality assurance

Nuclear power plants — Design against seismic hazards

Nuclear power plants — Reliability data exchange — General guidelines

Nuclear power plants — Guidelines to ensure quality of collected data on reliability

Nuclear criticality safety — Use of criticality accident alarm systems for operations

Nuclear power plants — Maintainability — Terminology

Determination of gas porosity and gas permeability of hydraulic binders containing embedded radioactive waste

Nuclear fuel technology — Administrative criteria related to nuclear criticality safety

Nuclear facilities — Ventilation penetrations for shielded enclosures

Nuclear facilities — Ventilation penetrations for shielded enclosures — Amendment 1

Nuclear criticality safety — Estimation of the number of fissions of a postulated criticality accident

Nuclear criticality safety — Estimation of the number of fissions of a postulated criticality accident — Amendment 1

Fusion installations — Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities

Nuclear facilities — Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning

Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 1: General requirements

Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 2: Radioactive CH3I method

Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 3: Cyclohexane gas leakage rate method

Nuclear facilities — Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors

Method for the justification of fire partitioning in water cooled nuclear power plants (NPP)

Reactor technology – Water cooled nuclear power plants (NPP) - Method for justification of fire partitioning

Fusion technology — Experimental magnetic confinement fusion facilities — Supersonic molecular beam injection fuelling technique for fusion devices

Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations — Part 1: Sampling of tritium and carbon-14

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

Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations — Part 3: Determination of tritium and carbon-14 activities sampled by molecular sieve

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

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

(U, Pu)O2 Powders and sintered pellets — Determination of chlorine and fluorine

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

Nuclear criticality safety — Nuclear criticality safety training for operations

Corrosion control engineering life cycle in nuclear power plants — General requirements

Design criteria for the thermal insulation of reactor coolant system main equipments and piping of PWR nuclear power plants

Ice plug isolation of piping in nuclear power plant

Management of radioactive waste from nuclear facilities — Part 1: General principles, objectives and practical approaches

Management of radioactive waste from nuclear facilities — Part 2: Predisposal

Nuclear energy — Nuclear fuel technology — Methodologies for radioactivity characterization of very low-level waste (VLLW) generated by nuclear facilities