Фильтр :
Стандарт и/или проект находящийся в компетенции ISO/TC 85/SC 2 Секретариата Этап 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
90.92
Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities
40.99
Radiation protection — Sealed radioactive sources — General requirements and classification
95.99
Radiological protection — Sealed radioactive sources — General requirements and classification
90.60
Unsealed radioactive substances — Identification and certification
95.99
Unsealed radioactive substances — Identification and documentation
90.93
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
90.93
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
60.60
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
60.60
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
60.60
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
60.60
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
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
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
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
90.92
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
40.20
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
60.60
Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials — Amendment 1
20.00
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
90.92
Decontamination of radioactively contaminated surfaces — Testing of decontamination agents for textiles
50.20
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
60.60
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
60.60
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
60.60
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
60.60
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
90.93
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
60.60
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
60.60
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
60.60
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
90.93
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
90.92
Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services
30.20
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
20.00
Radiological protection — Recommendations for dealing with discrepancies between personal dosimeter systems used in parallel
90.93
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
60.60
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
Nuclear installations — Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities
20.00
Nuclear facilities — Criteria for design and operation of confinement systems for nuclear worksite and for nuclear installations under decommissioning
60.60
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 1: General requirements
60.00
Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry
90.92
Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry
20.00
Nuclear facilities — Criteria for the design and operation of ventilation systems for nuclear installations other than nuclear reactors
90.93
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
90.60
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 the radioactivity in the environment — Bioindicator — Part 1: Part 1: General guide for the sampling,conditioning and pre-treatment
20.00
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
60.60
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
90.92
Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples
60.00
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
90.92
Measurement of radioactivity in the environment — Soil — Part 3: Test method of gamma-emitting radionuclides using gamma-ray spectrometry
40.99
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
60.60
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
60.60
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
60.60
Measurement of radioactivity in the environment — Soil — Part 7: In situ measurement of gamma-emitting radionuclides
90.93
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
90.92
Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics — The dicentric assay
40.60
Measurement of radioactivity — Determination of beta emitters activities — Test method using liquid scintillation counting
90.60
Radiological protection — Measurement for the clearance of waste contaminated with radioisotopes for medical application — Part 1: Measurement of radioactivity
60.60
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
90.20
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 by bubbling method
20.00
Measurement of radioactivity — Gamma-ray emitting radionuclides — Generic test method using gamma-ray spectrometry
60.60
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: Nuclear emergency exposure situation
40.60
Measurement of radioactivity in the environment — Air: aerosol particles — Test method using sampling by filter media
60.00
Measurement of the radioactivity in the environment – Air: tritium – Test Method using bubbler sampling
40.99
Radiological protection — Performance criteria for laboratories using Fluorescence In Situ Hybridization (FISH) translocation assay for assessment of exposure to ionizing radiation
60.60
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
20.00
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
90.92
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes
40.99
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 4: Validation of codes
60.60
Radiological protection — Low dose rate calibration of instruments for environmental and area monitoring
40.20
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
90.93
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
60.60
Monitoring for inadvertent movement and illicit trafficking of radioactive material
90.92
Monitoring for inadvertent movement and illicit trafficking of radioactive material
40.20
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
20.60
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
20.60
Radiological protection — General requirements for proficiency tests for in vivo radiobioassay
50.20
Development of a water equivalent phantom to measure the physical characteristics of specific radiosurgery treatment devices
60.00
Radiological protection — Format of input data for the statistical description of dose records of individuals monitored for occupational exposure to ionizing radiation
40.20
Radiological protection — Medical proton accelerators — Requirements and recommendations for shielding design and evaluation
30.99
Radiological protection — Radiological monitoring for emergency workers and population following nuclear/radiological incidents — Part 1: General principles
40.20
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
60.60
Radiation protection — Performance criteria for radiobioassay
90.93
Reference radiation fields for radiation protection — Definitions and fundamental concepts
90.93
Reference radiation fields for radiation protection — Definitions and fundamental concepts — Amendment 1: Reference point of personal dosemeters
60.60
Calibration and quality control in the use of radionuclide calibrators
20.00

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