Filter :
Standard and/or project under the direct responsibility of ISO/TC 85/SC 2 Secretariat | Stage | ICS |
---|---|---|
Personal photographic dosemeters
|
95.99 | |
General principles for sampling airborne radioactive materials
|
95.99 | |
Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities
|
95.99 | |
Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities
|
95.99 | |
Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities
|
60.60 | |
Radiation protection — Sealed radioactive sources — General requirements and classification
|
95.99 | |
Radiological protection — Sealed radioactive sources — General requirements and classification
|
90.93 | |
Unsealed radioactive substances — Identification and certification
|
95.99 | |
Unsealed radioactive substances — Identification and documentation
|
90.20 | |
Radiation protection — Apparatus for industrial gamma radiography — Part 1: Specifications for performance, design and tests
|
95.99 | |
Radiation protection — Apparatus for industrial gamma radiography — Specifications for performance, design and tests
|
90.60 | |
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
|
95.99 | |
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
|
90.93 | |
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
|
95.99 | |
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
|
90.93 | |
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
|
95.99 | |
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
|
90.93 | |
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
|
95.99 | |
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
|
90.93 | |
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
|
95.99 | |
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
|
95.99 | |
Sealed radioactive sources — Leak test methods
|
95.99 | |
Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production
|
95.99 | |
Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production
|
95.99 | |
Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production
|
60.60 | |
Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field
|
95.99 | |
Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field
|
95.99 | |
Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field
|
60.60 | |
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
|
95.99 | |
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
|
95.99 | |
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
|
60.60 | |
Reference beta radiations for calibrating dosemeters and doseratemeters and for determining their response as a function of beta radiation energy
|
95.99 | |
Reference beta radiations for calibrating dosemeters and dose-rate meters and for determining their response as a function of beta-radiation energy
|
95.99 | |
Radionuclide gauges — Gauges designed for permanent installation
|
95.99 | |
Enclosures for protection against ionizing radiation — Lead shielding units for 50 mm and 100 mm thick walls
|
90.93 | |
Evaluation of surface contamination — Part 1: Beta-emitters (maximum beta energy greater than 0,15 MeV) and alpha-emitters
|
95.99 | |
Measurement of radioactivity — Measurement and evaluation of surface contamination — Part 1: General principles
|
90.93 | |
Evaluation of surface contamination — Part 2: Tritium surface contamination
|
95.99 | |
Measurement of radioactivity - Measurement and evaluation of surface contamination — Part 2: Test method using wipe-test samples
|
90.93 | |
Evaluation of surface contamination — Part 3: Isomeric transition and electron capture emitters, low energy beta-emitters (E bêtamax less than 0,15 MeV)
|
95.99 | |
Measurement of radioactivity — Measurement and evaluation of surface contamination — Part 3: Apparatus calibration
|
90.93 | |
Radiation protection — Clothing for protection against radioactive contamination — Design, selection, testing and use
|
90.93 | |
Reference neutron radiations — Part 1: Characteristics and methods of production
|
95.99 | |
Reference neutron radiations — Part 1: Characteristics and methods of production — Technical Corrigendum 1
|
60.60 | |
Neutron reference radiations fields — Part 1: Characteristics and methods of production
|
60.60 | |
Reference neutron radiations — Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field
|
90.93 | |
Reference neutron radiations — Part 3: Calibration of area and personal dosimeters and determination of response as a function of energy and angle of incidence
|
95.99 | |
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
|
60.60 | |
Neutron reference radiations for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response as a function of neutron energy
|
95.99 | |
Decontamination of radioactively contaminated surfaces — Method for testing and assessing the ease of decontamination
|
95.99 | |
Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials
|
95.99 | |
Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials
|
60.60 | |
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
|
95.99 | |
Reference sources for the calibration of surface contamination monitors — Beta-emitters (maximum beta energy greater than 0,15 MeV) and alpha-emitters
|
95.99 | |
Reference sources — Calibration of surface contamination monitors — Alpha-, beta- and photon emitters
|
95.99 | |
Reference sources — Calibration of surface contamination monitors — Alpha-, beta- and photon emitters
|
95.99 | |
Measurement of radioactivity — Alpha-, beta- and photon emitting radionuclides — Reference measurement standard specifications for the calibration of surface contamination monitors
|
60.60 | |
Dosimetry of X and gamma reference radiations for radiation protection over the energy range from 8 keV to 1,3 MeV
|
95.99 | |
Decontamination of radioactively contaminated surfaces — Testing of decontamination agents for textiles
|
95.99 | |
Decontamination of radioactively contaminated surfaces — Testing of decontamination agents for textiles
|
60.60 | |
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
|
90.93 | |
Radiation protection — Sealed radioactive sources — Leakage test methods
|
95.99 | |
Radiation protection — Sealed sources — Leakage test methods
|
60.60 | |
Procedures for calibrating and determining the response of neutron-measuring devices used for radiation protection purposes
|
95.99 | |
Containment enclosures — Part 1: Design principles
|
90.93 | |
Containment enclosures — Part 2: Classification according to leak tightness and associated checking methods
|
90.93 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 1: Origins of radon and its short-lived decay products and associated measurement methods
|
95.99 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 1: Origins of radon and its short-lived decay products and associated measurement methods
|
90.20 | |
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
|
95.99 | |
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
|
90.20 | |
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
|
95.99 | |
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
|
60.60 | |
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
|
95.99 | |
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
|
95.99 | |
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
|
60.60 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 5: Continuous measurement method of the activity concentration
|
95.99 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 5: Continuous measurement methods of the activity concentration
|
60.60 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 6: Spot measurement method of the activity concentration
|
95.99 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 6: Spot measurement methods of the activity concentration
|
60.60 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 7: Accumulation method for estimating surface exhalation rate
|
90.93 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 8: Methodologies for initial and additional investigations in buildings
|
95.99 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 8: Methodologies for initial and additional investigations in buildings
|
90.20 | |
Measurement of radioactivity in the environment — Air: Radon-222 — Part 9: Test methods for exhalation rate of building materials
|
95.99 | |
Measurement of radioactivity in the environment — Air: Radon-222 — Part 9: Test methods for exhalation rate of building materials
|
90.60 | |
Measurement of radioactivity in the environment — Air: radon-222 — Part 11: Test method for soil gas with sampling at depth
|
90.93 | |
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
|
90.93 | |
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
|
90.92 | |
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
|
20.00 |
|
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
|
95.99 | |
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
|
90.92 | |
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
|
40.99 | |
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
|
95.99 | |
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
|
90.92 | |
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
|
40.99 | |
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
|
95.99 | |
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
|
90.92 | |
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
|
40.99 | |
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
|
95.99 | |
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
|
95.99 | |
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
|
60.60 | |
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
|
95.99 | |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 6: Fundamentals and applications to measurements by use of transient mode
|
95.99 | |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 7: Fundamentals and general applications
|
95.99 | |
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
|
95.99 | |
Determination of the characteristic limits (decision threshold, detection limit and limits of the confidence interval) for measurements of ionizing radiation — Fundamentals and application
|
95.99 | |
Components for containment enclosures — Part 1: Glove/bag ports, bungs for glove/bag ports, enclosure rings and interchangeable units
|
90.93 | |
Components for containment enclosures — Part 2: Gloves, welded bags, gaiters for remote - handling tongs and for manipulators
|
90.93 | |
Components for containment enclosures — Part 3: Transfer systems such as plain doors, airlock chambers, double door transfer systems, leaktight connections for waste drums
|
90.93 | |
Components for containment enclosures — Part 4: Ventilation and gas-cleaning systems such as filters, traps, safety and regulation valves, control and protection devices
|
90.93 | |
Components for containment enclosures — Part 5: Penetrations for electrical and fluid circuits
|
90.92 | |
Components for containment enclosures — Part 5: Penetrations for electrical and fluid circuits
|
30.99 |
|
X and gamma radiation — Indirect- or direct- reading capacitor-type pocket dosemeters
|
95.99 | |
Reference radiation fields — Simulated workplace neutron fields — Part 1: Characteristics and methods of production
|
90.93 | |
Reference radiation fields — Simulated workplace neutron fields — Part 2: Calibration fundamentals related to the basic quantities
|
90.93 | |
Reference neutron radiations — Characteristics and methods of production of simulated workplace neutron fields
|
95.99 | |
Radiation protection — Performance criteria for radiobioassay — Part 1: General principles
|
95.99 | |
Nuclear energy — Radiation protection — Individual thermoluminescence dosemeters for extremities and eyes
|
95.99 | |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 1: General principles
|
95.99 | |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 1: General principles
|
60.60 | |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 2: Ex vivo human tooth enamel dosimetry
|
60.60 | |
Radiation protection — Criteria and performance limits for the periodic evaluation of processors of personal dosemeters for X and gamma radiation
|
95.99 | |
Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services
|
95.99 | |
Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services for external radiation
|
60.60 | |
Neutron radiation protection shielding — Design principles and considerations for the choice of appropriate materials
|
90.93 | |
Neutron radiation protection shielding — Design principles and considerations for the choice of appropriate materials — Technical Corrigendum 1
|
60.60 | |
Nuclear facilities — Ventilation penetrations for shielded enclosures
|
90.93 | |
Nuclear facilities — Ventilation penetrations for shielded enclosures — Amendment 1
|
60.60 | |
Nuclear energy — Radiationprotection — Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation
|
95.99 | |
Radiological protection — Procedures for monitoring the dose to the lens of the eye, the skin and the extremities
|
90.92 | |
Radiological protection — Procedures for monitoring the dose to the lens of the eye, the skin and the extremities
|
40.20 | |
Radiological protection — Recommendations for dealing with discrepancies between personal dosimeter systems used in parallel
|
90.60 | |
Radiological protection — Monitoring and internal dosimetry for staff members exposed to medical radionuclides as unsealed sources
|
90.93 | |
Radiological protection — Monitoring and internal dosimetry for specific materials — Part 1: Inhalation of uranium compounds
|
90.93 | |
Radiological protection — Monitoring and internal dosimetry for specific materials — Part 2: Ingestion of uranium compounds
|
90.20 | |
Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities
|
90.93 | |
Monitoring radioactive gases in effluents from facilities producing positron emitting radionuclides and radiopharmaceuticals
|
60.60 | |
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
|
90.93 | |
Radiological protection — Medical electron accelerators — Requirements and recommendations for shielding design and evaluation
|
90.93 | |
Fusion installations — Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities
|
60.60 | |
Nuclear facilities — Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning
|
90.93 | |
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 1: General requirements
|
60.60 | |
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 2: Radioactive CH3I method
|
30.60 | |
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 3: Cyclohexane gas leakage rate method
|
30.60 |
|
Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry
|
95.99 | |
Radiological protection — Performance criteria for laboratories using the cytokinesis-block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry
|
60.60 | |
Nuclear facilities — Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
|
90.60 | |
Remote handling devices for radioactive materials — Part 1: General requirements
|
95.99 | |
Remote handling devices for radioactive materials — Part 1: General requirements
|
90.93 | |
Remote-handling devices for radioactive materials — Part 2: Mechanical master-slave manipulators
|
90.93 | |
Remote handling devices for radioactive materials — Part 3: Electrical master-slave manipulators
|
90.93 | |
Remote handling devices for radioactive materials — Part 4: Power manipulators
|
90.93 | |
Remote handling devices for radioactive materials — Part 5: Remote handling tongs
|
90.93 | |
Radiological protection — Characteristics of reference pulsed radiation — Part 1: Photon radiation
|
30.99 | |
Radiological protection — Characteristics of reference pulsed radiation — Part 1: Photon radiation
|
90.92 | |
Measurement and prediction of the ambient dose equivalent from patients receiving iodine 131 administration after thyroid ablation — Part 1: During the hospitalization
|
90.93 | |
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
|
60.60 | |
Iodine charcoal sorbents for nuclear facilities — Method for defining sorption capacity index
|
90.93 | |
Measurement of radioactivity in the environment — Bioindicators — Part 1: General guide for the sampling, conditioning and pre-treatment
|
40.60 | |
Magnetic fusion facilities — Requirements for the safety systems raised by the application of the superconducting technology
|
40.60 | |
Measurement of radioactivity in the environment — Soil — Part 1: General guidelines and definitions
|
95.99 | |
Measurement of radioactivity in the environment — Soil — Part 1: General guidelines and definitions
|
90.20 | |
Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples
|
95.99 | |
Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples
|
95.99 | |
Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples
|
60.60 | |
Measurement of radioactivity in the environment — Soil — Part 3: Measurement of gamma-emitting radionuclides
|
95.99 | |
Measurement of radioactivity in the environment — Soil — Part 3: Test method of gamma-emitting radionuclides using gamma-ray spectrometry
|
95.99 | |
Measurement of radioactivity in the environment — Soil — Part 3: Test method of gamma-emitting radionuclides using gamma-ray spectrometry
|
60.60 | |
Measurement of radioactivity in the environment — Soil — Part 4: Measurement of plutonium isotopes (plutonium 238 and plutonium 239 + 240) by alpha spectrometry
|
95.99 | |
Measurement of radioactivity in the environment — Soil — Part 4: Plutonium 238 and plutonium 239 + 240 — Test method using alpha spectrometry
|
90.20 | |
Measurement of radioactivity in the environment — Soil — Part 5: Measurement of strontium 90
|
95.99 | |
Measurement of radioactivity in the environment — Soil — Part 5: Strontium 90 — Test method using proportional counting or liquid scintillation counting
|
90.20 | |
Measurement of radioactivity in the environment — Soil — Part 6: Measurement of gross alpha and gross beta activities
|
95.99 | |
Measurement of radioactivity in the environment — Soil — Part 6: Gross alpha and gross beta activities — Test method using gas-flow proportional counting
|
90.20 | |
Measurement of radioactivity in the environment — Soil — Part 7: In situ measurement of gamma-emitting radionuclides
|
90.92 | |
Measurement of radioactivity in the environment — Soil — Part 7: In situ measurement of gamma-emitting radionuclides
|
40.99 | |
Measurement of radioactivity in urine-238Pu, 239Pu and 240Pu-Test method using alpha spectrometry and ICP-MS
|
30.60 |
|
Radiation protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics
|
95.99 | |
Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics
|
95.99 | |
Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics — Dicentric assay
|
60.60 | |
Measurement of radioactivity — Determination of beta emitters activities — Test method using liquid scintillation counting
|
90.92 | |
Measurement of radioactivity — Determination of beta emitters activities — Test method using liquid scintillation counting
|
40.20 | |
Radiological protection — Measurement for the clearance of waste contaminated with radioisotopes for medical application — Part 1: Measurement of radioactivity
|
90.93 | |
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
|
60.60 | |
Measurement of radioactivity — Gamma emitting radionuclides — Rapid screening method using scintillation detector gamma-ray spectrometry
|
90.92 | |
Measurement of radioactivity — Gamma emitting radionuclides — Rapid screening method using scintillation detector gamma-ray spectrometry
|
40.20 | |
Radiological protection — Monitoring and dosimetry for internal exposures due to wound contamination with radionuclides
|
60.60 | |
Tritium and carbon-14 activity in gaseous effluents and gas discharges of nuclear installations — Part 1: Sampling of tritium and carbon-14
|
60.60 | |
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 | |
Measurement of radioactivity — Gamma-ray emitting radionuclides — Generic test method using gamma-ray spectrometry
|
90.93 | |
Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 1: Planned and existing exposure situation
|
60.60 | |
Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 2: Emergency exposure situation
|
60.60 | |
Measurement of radioactivity in the environment — Air: aerosol particles — Test method using sampling by filter media
|
60.60 | |
Measurement of the radioactivity in the environment — Air: tritium — Test method using bubbler sampling
|
60.60 | |
Radiological protection — Performance criteria for laboratories using Fluorescence In Situ Hybridization (FISH) translocation assay for assessment of exposure to ionizing radiation
|
90.93 | |
Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material
|
90.92 | |
Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material
|
50.20 | |
Dosemetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements
|
95.99 | |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements
|
95.99 | |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements
|
60.60 | |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 2: Characterization of instrument response
|
95.99 | |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 2: Characterization of instrument response
|
60.60 | |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes
|
95.99 | |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes
|
60.60 | |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 4: Validation of codes
|
90.60 | |
Radiological protection — Low dose rate calibration of instruments for environmental and area monitoring
|
60.60 | |
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 | |
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 | |
Clinical dosimetry — Beta radiation sources for brachytherapy
|
90.20 | |
Ionizing-radiation warning — Supplementary symbol
|
90.93 | |
Passive neutron dosimetry systems — Part 1: Performance and test requirements for personal dosimetry
|
95.99 | |
Passive neutron dosimetry systems — Part 1: Performance and test requirements for personal dosimetry
|
60.60 | |
Passive neutron dosimetry systems — Part 2: Methodology and criteria for the qualification of personal dosimetry systems in workplaces
|
60.60 | |
Passive personal neutron dosemeters — Performance and test requirements
|
95.99 | |
Passive personal neutron dosemeters — Performance and test requirements — Technical Corrigendum 1
|
95.99 | |
Dosimetry with radiophotoluminescent glass dosimeters for dosimetry audit in MV X-ray radiotherapy
|
90.20 | |
Monitoring for inadvertent movement and illicit trafficking of radioactive material
|
95.99 | |
Monitoring for inadvertent movement and illicit trafficking of radioactive material
|
60.60 | |
Radiological protection — Assessment of external exposures to individuals in case of radiological or nuclear emergencies
|
20.00 |
|
Evaluating the performance of continuous air monitors — Part 1: Air monitors based on accumulation sampling techniques
|
60.60 | |
Evaluating the performance of continuous air monitors — Part 2: Air monitors based on flow-through sampling techniques without accumulation
|
60.60 | |
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
|
20.98 |
|
Measurement of radioactivity — Gamma emitting radionuclides — Reference measurement standard specifications for the calibration of gamma-ray spectrometers
|
60.60 | |
Measurement of radioactivity — Alpha emitting radionuclides — Generic test method using alpha spectrometry
|
60.60 | |
Radiological protection — General requirements for proficiency tests for in vivo radiobioassay
|
60.60 | |
Development of a water equivalent phantom to measure the physical characteristics of specific radiosurgery treatment devices
|
60.60 | |
Radiological protection — Content of input data for the statistical analysis of dose records of individuals monitored for occupational exposure to ionizing radiation
|
60.60 | |
Radiological protection — Medical proton accelerators — Requirements and recommendations for shielding design and evaluation
|
40.60 | |
Radiological protection — Radiological monitoring for emergency workers and population following nuclear/radiological incidents — General principles
|
60.60 | |
Monitoring and internal dose assessment for radiation workers handling plutonium
|
20.00 |
|
Nuclear facilities — Criteria for the design and the operation of containment and ventilation systems for nuclear reactors
|
90.93 | |
Radiation protection — Dose assessment for the monitoring of workers for internal radiation exposure
|
90.93 | |
Dosimetry with solid thermoluminescence detectors for photon and electron radiations in radiotherapy
|
95.99 | |
Clinical dosimetry — Dosimetry with solid thermoluminescence detectors for photon and electron radiations in radiotherapy
|
90.93 | |
Radiation protection — Performance criteria for radiobioassay
|
90.93 | |
Reference radiation fields for radiation protection — Definitions and fundamental concepts
|
90.92 | |
Reference radiation fields for radiation protection — Definitions and fundamental concepts — Amendment 1: Reference point of personal dosemeters
|
60.60 | |
Reference radiation fields for radiation protection — Definitions and fundamental concepts
|
20.00 |
|
Calibration and quality control in the use of radionuclide calibrators
|
30.99 |
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