Personal photographic dosemeters

General principles for sampling airborne radioactive materials

Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities

Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities

Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities

Radiation protection — Sealed radioactive sources — General requirements and classification

Radiological protection — Sealed radioactive sources — General requirements and classification

Unsealed radioactive substances — Identification and certification

Unsealed radioactive substances — Identification and documentation

Radiation protection — Apparatus for industrial gamma radiography — Part 1: Specifications for performance, design and tests

Radiation protection — Apparatus for industrial gamma radiography — Specifications for performance, design and tests

X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 1: Radiation characteristics and production methods

Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 1: Radiation characteristics and production methods

X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 2: Dosimetry for radiation protection over the energy ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV

Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 2: Dosimetry for radiation protection over the energy ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV

X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 3: Calibration of area and personal dosemeters and the measurement of their response as a function of energy and angle of incidence

Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 3: Calibration of area and personal dosemeters and the measurement of their response as a function of energy and angle of incidence

X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 4: Calibration of area and personal dosemeters in low energy X reference radiation fields

Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 4: Calibration of area and personal dosemeters in low energy X reference radiation fields

X and gamma reference radiations for calibrating dosemeters and dose ratemeters and for determining their response as a function of photon energy — Amendment 1: Low rate series of filtered X-radiations

X and gamma reference radiations for calibrating dosemeters and dose ratemeters and for determining their response as a function of photon energy — Addendum 2: Photon reference radiations at energies between 4 MeV and 9 MeV

Sealed radioactive sources — Leak test methods

Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production

Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production

Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production

Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field

Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field

Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field

Nuclear energy — Reference beta-particle radiation — Part 3: Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence

Nuclear energy — Reference beta-particle radiation — Part 3: Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence

Nuclear energy — Reference beta-particle radiation — Part 3: Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence

Reference beta radiations for calibrating dosemeters and doseratemeters and for determining their response as a function of beta radiation energy

Reference beta radiations for calibrating dosemeters and dose-rate meters and for determining their response as a function of beta-radiation energy

Radionuclide gauges — Gauges designed for permanent installation

Enclosures for protection against ionizing radiation — Lead shielding units for 50 mm and 100 mm thick walls

Evaluation of surface contamination — Part 1: Beta-emitters (maximum beta energy greater than 0,15 MeV) and alpha-emitters

Measurement of radioactivity — Measurement and evaluation of surface contamination — Part 1: General principles

Evaluation of surface contamination — Part 2: Tritium surface contamination

Measurement of radioactivity - Measurement and evaluation of surface contamination — Part 2: Test method using wipe-test samples

Evaluation of surface contamination — Part 3: Isomeric transition and electron capture emitters, low energy beta-emitters (E bêtamax less than 0,15 MeV)

Measurement of radioactivity — Measurement and evaluation of surface contamination — Part 3: Apparatus calibration

Radiation protection — Clothing for protection against radioactive contamination — Design, selection, testing and use

Reference neutron radiations — Part 1: Characteristics and methods of production

Reference neutron radiations — Part 1: Characteristics and methods of production — Technical Corrigendum 1

Neutron reference radiations fields — Part 1: Characteristics and methods of production

Reference neutron radiations — Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field

Reference neutron radiations — Part 3: Calibration of area and personal dosimeters and determination of response as a function of energy and angle of incidence

Neutron reference radiation fields — Part 3: Calibration of area and personal dosemeters and determination of their response as a function of neutron energy and angle of incidence

Neutron reference radiations for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response as a function of neutron energy

Decontamination of radioactively contaminated surfaces — Method for testing and assessing the ease of decontamination

Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials

Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials — Amendment 1

Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials

Reference sources for the calibration of surface contamination monitors — Part 2: Electrons of energy less than 0,15 MeV and photons of energy less than 1,5 MeV

Reference sources for the calibration of surface contamination monitors — Beta-emitters (maximum beta energy greater than 0,15 MeV) and alpha-emitters

Reference sources — Calibration of surface contamination monitors — Alpha-, beta- and photon emitters

Reference sources — Calibration of surface contamination monitors — Alpha-, beta- and photon emitters

Measurement of radioactivity — Alpha-, beta- and photon emitting radionuclides — Reference measurement standard specifications for the calibration of surface contamination monitors

Dosimetry of X and gamma reference radiations for radiation protection over the energy range from 8 keV to 1,3 MeV

Decontamination of radioactively contaminated surfaces — Testing of decontamination agents for textiles

Decontamination of radioactively contaminated surfaces — Testing of decontamination agents for textiles

Enclosures for protection against ionizing radiation — Lead shielding units for 150 mm, 200 mm and 250 mm thick walls — Part 1: Chevron units of 150 mm and 200 mm thickness

Radiation protection — Sealed radioactive sources — Leakage test methods

Radiation protection — Sealed sources — Leakage test methods

Procedures for calibrating and determining the response of neutron-measuring devices used for radiation protection purposes

Containment enclosures — Part 1: Design principles

Containment enclosures — Part 2: Classification according to leak tightness and associated checking methods

Measurement of radioactivity in the environment — Air: radon-222 — Part 1: Origins of radon and its short-lived decay products and associated measurement methods

Measurement of radioactivity in the environment — Air: radon-222 — Part 1: Origins of radon and its short-lived decay products and associated measurement methods

Measurement of radioactivity in the environment — Air: radon-222 — Part 2: Integrated measurement method for determining average potential alpha energy concentration of its short-lived decay products

Measurement of radioactivity in the environment — Air: radon-222 — Part 2: Integrated measurement method for determining average potential alpha energy concentration of its short-lived decay products

Measurement of radioactivity in the environment — Air: radon-222 — Part 3: Spot measurement method of the potential alpha energy concentration of its short-lived decay products

Measurement of radioactivity in the environment — Air: radon-222 — Part 3: Spot measurement method of the potential alpha energy concentration of its short-lived decay products

Measurement of radioactivity in the environment — Air: radon-222 — Part 4: Integrated measurement method for determining average activity concentration using passive sampling and delayed analysis

Measurement of radioactivity in the environment — Air: radon-222 — Part 4: Integrated measurement method for determining average activity concentration using passive sampling and delayed analysis

Measurement of radioactivity in the environment — Air: radon-222 — Part 4: Integrated measurement method for determining average activity concentration using passive sampling and delayed analysis

Measurement of radioactivity in the environment — Air: radon-222 — Part 5: Continuous measurement method of the activity concentration

Measurement of radioactivity in the environment — Air: radon-222 — Part 5: Continuous measurement methods of the activity concentration

Measurement of radioactivity in the environment — Air: radon-222 — Part 6: Spot measurement method of the activity concentration

Measurement of radioactivity in the environment — Air: radon-222 — Part 6: Spot measurement methods of the activity concentration

Measurement of radioactivity in the environment — Air: radon-222 — Part 7: Accumulation method for estimating surface exhalation rate

Measurement of radioactivity in the environment — Air: radon-222 — Part 8: Methodologies for initial and additional investigations in buildings

Measurement of radioactivity in the environment — Air: radon-222 — Part 8: Methodologies for initial and additional investigations in buildings

Measurement of radioactivity in the environment — Air: Radon-222 — Part 9: Test methods for exhalation rate of building materials

Measurement of radioactivity in the environment — Air: Radon-222 — Part 9: Test methods for exhalation rate of building materials

Measurement of radioactivity in the environment — Air: radon-222 — Part 11: Test method for soil gas with sampling at depth

Measurement of radioactivity in the environment — Air: radon-222 — Part 12: Determination of the diffusion coefficient in waterproof materials: membrane one-side activity concentration measurement method

Measurement of radioactivity in the environment — Air: radon 222 — Part 13: Determination of the diffusion coefficient in waterproof materials: membrane two-side activity concentration test method

Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 1: Fundamentals and application to counting measurements without the influence of sample treatment

Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 1: Elementary applications

Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 2: Fundamentals and application to counting measurements with the influence of sample treatment

Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 2: Advanced applications

Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 3: Fundamentals and application to counting measurements by high resolution gamma spectrometry, without the influence of sample treatment

Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 3: Applications to unfolding methods

Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 4: Fundamentals and application to measurements by use of linear-scale analogue ratemeters, without the influence of sample treatment

Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 4: Guidelines to applications

Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 4: Guidelines to applications

Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 5: Fundamentals and applications to counting measurements on filters during accumulation of radioactive material

Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 6: Fundamentals and applications to measurements by use of transient mode

Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 7: Fundamentals and general applications

Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 8: Fundamentals and application to unfolding of spectrometric measurements without the influence of sample treatment

Determination of the characteristic limits (decision threshold, detection limit and limits of the confidence interval) for measurements of ionizing radiation — Fundamentals and application

Components for containment enclosures — Part 1: Glove/bag ports, bungs for glove/bag ports, enclosure rings and interchangeable units

Components for containment enclosures — Part 2: Gloves, welded bags, gaiters for remote - handling tongs and for manipulators

Components for containment enclosures — Part 3: Transfer systems such as plain doors, airlock chambers, double door transfer systems, leaktight connections for waste drums

Components for containment enclosures — Part 4: Ventilation and gas-cleaning systems such as filters, traps, safety and regulation valves, control and protection devices

Components for containment enclosures — Part 5: Penetrations for electrical and fluid circuits

X and gamma radiation — Indirect- or direct- reading capacitor-type pocket dosemeters

Reference radiation fields — Simulated workplace neutron fields — Part 1: Characteristics and methods of production

Reference radiation fields — Simulated workplace neutron fields — Part 2: Calibration fundamentals related to the basic quantities

Reference neutron radiations — Characteristics and methods of production of simulated workplace neutron fields

Radiation protection — Performance criteria for radiobioassay — Part 1: General principles

Nuclear energy — Radiation protection — Individual thermoluminescence dosemeters for extremities and eyes

Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 1: General principles

Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 1: General principles

Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 2: Ex vivo human tooth enamel dosimetry

Radiation protection — Criteria and performance limits for the periodic evaluation of processors of personal dosemeters for X and gamma radiation

Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services

Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services

Neutron radiation protection shielding — Design principles and considerations for the choice of appropriate materials

Neutron radiation protection shielding — Design principles and considerations for the choice of appropriate materials — Technical Corrigendum 1

Nuclear facilities — Ventilation penetrations for shielded enclosures

Nuclear facilities — Ventilation penetrations for shielded enclosures — Amendment 1

Nuclear energy — Radiationprotection — Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation

Radiological protection — Procedures for monitoring the dose to the lens of the eye, the skin and the extremities

Radiological protection — Procedures for monitoring the dose to the lens of the eye, the skin and the extremities

Radiological protection — Recommendations for dealing with discrepancies between personal dosimeter systems used in parallel

Radiological protection — Monitoring and internal dosimetry for staff members exposed to medical radionuclides as unsealed sources

Radiological protection — Monitoring and internal dosimetry for specific materials — Part 1: Inhalation of uranium compounds

Radiological protection — Monitoring and internal dosimetry for specific materials — Part 2: Ingestion of uranium compounds

Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities

Monitoring radioactive gases in effluents from facilities producing positron emitting radionuclides and radiopharmaceuticals

Measurement of radioactivity in the environment — Air — Radon 220: Integrated measurement methods for the determination of the average activity concentration using passive solid-state nuclear track detectors

Radiological protection — Medical electron accelerators — Requirements and recommendations for shielding design and evaluation

Nuclear 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 method

Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry

Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry

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

Remote handling devices for radioactive materials — Part 1: General requirements

Remote handling devices for radioactive materials — Part 1: General requirements

Remote-handling devices for radioactive materials — Part 2: Mechanical master-slave manipulators

Remote handling devices for radioactive materials — Part 3: Electrical master-slave manipulators

Remote handling devices for radioactive materials — Part 4: Power manipulators

Remote handling devices for radioactive materials — Part 5: Remote handling tongs

Radiological protection — Characteristics of reference pulsed radiation — Part 1: Photon radiation

Radiological protection — Characteristics of reference pulsed radiation — Part 1: Photon radiation

Measurement and prediction of the ambient dose equivalent from patients receiving iodine 131 administration after thyroid ablation — Part 1: During the hospitalization

Measurement and prediction of the ambient dose equivalent from patients receiving iodine 131 administration after thyroid ablation — Part 2: External effective dose of the caregivers after release from the hospital

Iodine charcoal sorbents for nuclear facilities — Method for defining sorption capacity index

Measurement of the radioactivity in the environment — Bioindicator — Part 1: Part 1: General guide for the sampling,conditioning and pre-treatment

Requirements to the safety systems raised by the application of the superconducting technology in nuclear fusion facilities.

Measurement of radioactivity in the environment — Soil — Part 1: General guidelines and definitions

Measurement of radioactivity in the environment — Soil — Part 1: General guidelines and definitions

Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples

Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples

Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples

Measurement of radioactivity in the environment — Soil — Part 3: Measurement of gamma-emitting radionuclides

Measurement of radioactivity in the environment — Soil — Part 3: Test method of gamma-emitting radionuclides using gamma-ray spectrometry

Measurement of radioactivity in the environment — Soil — Part 3: Test method of gamma-emitting radionuclides using gamma-ray spectrometry

Measurement of radioactivity in the environment — Soil — Part 4: Measurement of plutonium isotopes (plutonium 238 and plutonium 239 + 240) by alpha spectrometry

Measurement of radioactivity in the environment — Soil — Part 4: Plutonium 238 and plutonium 239 + 240 — Test method using alpha spectrometry

Measurement of radioactivity in the environment — Soil — Part 5: Measurement of strontium 90

Measurement of radioactivity in the environment — Soil — Part 5: Strontium 90 — Test method using proportional counting or liquid scintillation counting

Measurement of radioactivity in the environment — Soil — Part 6: Measurement of gross alpha and gross beta activities

Measurement of radioactivity in the environment — Soil — Part 6: Gross alpha and gross beta activities — Test method using gas-flow proportional counting

Measurement of radioactivity in the environment — Soil — Part 7: In situ measurement of gamma-emitting radionuclides

Measurement of radioactivity in urine-238Pu, 239Pu and 240Pu-Test method using alpha spectrometry and ICP-MS

Radiation protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics

Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics

Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics — Dicentric assay

Measurement of radioactivity — Determination of beta emitters activities — Test method using liquid scintillation counting

Measurement of radioactivity — Determination of beta emitters activities — Test method using liquid scintillation counting

Radiological protection — Measurement for the clearance of waste contaminated with radioisotopes for medical application — Part 1: Measurement of radioactivity

Radiological protection — Measurement for the clearance of waste contaminated with radioisotopes for medical application — Part 2: Management of solid radioactive waste in nuclear medicine facilities

Measurement of radioactivity — Gamma emitting radionuclides — Rapid screening method using scintillation detector gamma-ray spectrometry

Measurement of radioactivity — Gamma emitting radionuclides — Rapid screening method using scintillation detector gamma-ray spectrometry

Radiological protection — Monitoring and dosimetry for internal exposures due to wound contamination with radionuclides

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 by bubbling method

Measurement of radioactivity — Gamma-ray emitting radionuclides — Generic test method using gamma-ray spectrometry

Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 1: Planned and existing exposure situation

Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 2: Emergency exposure situation

Measurement of radioactivity in the environment — Air: aerosol particles — Test method using sampling by filter media

Measurement of the radioactivity in the environment — Air: tritium — Test method using bubbler sampling

Radiological protection — Performance criteria for laboratories using Fluorescence In Situ Hybridization (FISH) translocation assay for assessment of exposure to ionizing radiation

Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material

Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material

Dosemetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements

Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements

Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements

Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 2: Characterization of instrument response

Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 2: Characterization of instrument response

Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes

Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes

Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 4: Validation of codes

Radiological protection — Low dose rate calibration of instruments for environmental and area monitoring

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

Clinical dosimetry — Beta radiation sources for brachytherapy

Ionizing-radiation warning — Supplementary symbol

Passive neutron dosimetry systems — Part 1: Performance and test requirements for personal dosimetry

Passive neutron dosimetry systems — Part 1: Performance and test requirements for personal dosimetry

Passive neutron dosimetry systems — Part 2: Methodology and criteria for the qualification of personal dosimetry systems in workplaces

Passive personal neutron dosemeters — Performance and test requirements

Passive personal neutron dosemeters — Performance and test requirements — Technical Corrigendum 1

Dosimetry with radiophotoluminescent glass dosimeters for dosimetry audit in MV X-ray radiotherapy

Monitoring for inadvertent movement and illicit trafficking of radioactive material

Monitoring for inadvertent movement and illicit trafficking of radioactive material

Evaluating the performance of continuous air monitors — Part 1: Air monitors based on accumulation sampling techniques

Evaluating the performance of continuous air monitors — Part 2: Air monitors based on flow-through sampling techniques without accumulation

Measurement of radioactivity in the environment — Air: Radon-222 — Quality assurance/quality control for calibration facilities, radon measurement device manufacturers and measurement device analysis providers

Measurement of radioactivity — Gamma emitting radionuclides — Reference measurement standard specifications for the calibration of gamma-ray spectrometers

Measurement of radioactivity — Alpha emitting radionuclides — Generic test method using alpha spectrometry

Radiological protection — General requirements for proficiency tests for in vivo radiobioassay

Development of a water equivalent phantom to measure the physical characteristics of specific radiosurgery treatment devices

Radiological protection — Content of input data for the statistical analysis of dose records of individuals monitored for occupational exposure to ionizing radiation

Radiological protection — Medical proton accelerators — Requirements and recommendations for shielding design and evaluation

Radiological protection — Radiological monitoring for emergency workers and population following nuclear/radiological incidents — General principles

Nuclear facilities — Criteria for the design and the operation of containment and ventilation systems for nuclear reactors

Radiation protection — Dose assessment for the monitoring of workers for internal radiation exposure

Dosimetry with solid thermoluminescence detectors for photon and electron radiations in radiotherapy

Clinical dosimetry — Dosimetry with solid thermoluminescence detectors for photon and electron radiations in radiotherapy

Radiation protection — Performance criteria for radiobioassay

Reference radiation fields for radiation protection — Definitions and fundamental concepts

Reference radiation fields for radiation protection — Definitions and fundamental concepts — Amendment 1: Reference point of personal dosemeters

Calibration and quality control in the use of radionuclide calibrators