| Name |
Description |
Abstract |
Status |
Publication date |
Edition |
Number of pages |
Technical committee |
ICS |
| ISO 12749-3:2015 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 3: Nuclear fuel cycle |
ISO 12749-3:2015 lists unambiguous terms and definitions related to nuclear fuel cycle concepts in the subject field of nuclear energy, excluding reactor operations. It is intended to facilitate communication and promote common understanding.
|
Published |
2015-08 |
Edition : 1 |
Number of pages : 36 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
|
| ISO 12749-4:2015 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 4: Dosimetry for radiation processing |
ISO 12749-4:2015 lists unambiguous terms and definitions for concepts for dosimetry related to radiation processing using gamma radiation, X-radiation, or accelerated electrons. It is intended to facilitate communication and promote common understanding.
|
Published |
2015-08 |
Edition : 1 |
Number of pages : 29 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
|
| ISO 12749-5:2018 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 5: Nuclear reactors |
ISO 12749-5:2018 encompasses the collection of terms, definitions, notes and examples corresponding to nuclear reactors, excluding quantitative data. It provides the minimum essential information for each nuclear reactor concept represented by a single term. Full understanding of concepts requires background knowledge of the nuclear field. It is intended to facilitate communication and promote common understanding.
The scope of ISO 12749-5:2018 covers the whole field of nuclear reactors at a broad surface level.
|
Published |
2018-02 |
Edition : 1 |
Number of pages : 54 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
|
| ISO 12749-6:2020 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 6: Nuclear medicine |
This document contains the terms, definitions, notes to entry and examples corresponding to the frequently used concepts which apply to diagnostic and therapeutic nuclear medicine.
It comprises the minimum essential information for each nuclear medicine concept represented by a single term. It provides the reader with the information required to approach this multidisciplinary speciality, such as medical, radiopharmacy and medical physics point of view. It is intended to facilitate communication and promote common understanding.
|
Published |
2020-11 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
01.040.11
Health care technology (Vocabularies)
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
;
11.020.20
Medical science
|
| ISO 12790-1:2001 |
Radiation protection — Performance criteria for radiobioassay — Part 1: General principles |
|
Withdrawn |
2001-12 |
Edition : 1 |
Number of pages : 31 |
Technical Committee |
13.280
Radiation protection
|
| ISO 12794:2000 |
Nuclear energy — Radiation protection — Individual thermoluminescence dosemeters for extremities and eyes |
|
Withdrawn |
2000-03 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
13.280
Radiation protection
|
| ISO 12807:1996 |
Safe transport of radioactive materials — Leakage testing on packages |
|
Withdrawn |
1996-10 |
Edition : 1 |
Number of pages : 76 |
Technical Committee |
13.280
Radiation protection
;
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 21909:2005 |
Passive personal neutron dosemeters — Performance and test requirements |
ISO 21909:2005 provides performance and test requirements for determining the acceptability of personal neutron dosemeters to be used for the measurement of personal dose equivalent, Hp(10) for neutrons ranging in energy from thermal to 20 MeV.
|
Withdrawn |
2005-06 |
Edition : 1 |
Number of pages : 50 |
Technical Committee |
13.280
Radiation protection
|
| ISO 12807:2018 |
Safe transport of radioactive materials — Leakage testing on packages |
This document specifies gas leakage test criteria and test methods for demonstrating that packages used to transport radioactive materials comply with the package containment requirements defined in the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material for:
— design verification;
— fabrication verification;
— preshipment verification;
— periodic verification;
— maintenance verification.
This document describes a method for relating permissible activity release of the radioactive contents carried within a containment system to equivalent gas leakage rates under specified test conditions. This approach is called gas leakage test methodology. However, in this document it is recognized that other methodologies might be acceptable, provided that they demonstrate that any release of the radioactive contents will not exceed the regulatory requirements, and subject to agreement with the competent authority.
This document provides both overall and detailed guidance on the complex relationships between an equivalent gas leakage test and a permissible activity release rate. Whereas the overall guidance is universally agreed upon, the use of the detailed guidance shall be agreed upon with the competent authority during the Type B(U), Type B(M) or Type C packages certification process.
It should be noted that, for a given package, demonstration of compliance is not limited to a single methodology.
While this document does not require particular gas leakage test procedures, it does present minimum requirements for any test that is to be used. It is the responsibility of the package designer or consignor to estimate or determine the maximum permissible release rate of radioactivity to the environment and to select appropriate leakage test procedures that have adequate sensitivity.
This document pertains specifically to Type B(U), Type B(M) or Type C packages for which the regulatory containment requirements are specified explicitly.
|
Published |
2018-09 |
Edition : 2 |
Number of pages : 85 |
Technical Committee |
13.280
Radiation protection
;
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 13164-1:2013 |
Water quality — Radon-222 — Part 1: General principles |
ISO 13164-1:2013 gives general guidelines for sampling, packaging, and transporting of all kinds of water samples, for the measurement of the activity concentration of radon-222.
The test methods fall into two categories: a) direct measurement of the water sample without any transfer of phase (see ISO 13164‑2); b) indirect measurement involving the transfer of the radon-222 from the aqueous phase to another phase (see ISO 13164‑3).
The test methods can be applied either in the laboratory or on site.
The laboratory is responsible for ensuring the suitability of the test method for the water samples tested.
|
Published |
2013-09 |
Edition : 1 |
Number of pages : 25 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-2:2013 |
Water quality — Radon-222 — Part 2: Test method using gamma-ray spectrometry |
ISO 13164-2:2013 specifies a test method for the determination of radon-222 activity concentration in a sample of water following the measurement of its short-lived decay products by direct gamma-spectrometry of the water sample.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available gamma-ray instruments, range from a few becquerels per litre to several hundred thousand becquerels per litre for a 1 l test sample.
This test method can be used successfully with drinking water samples. The laboratory is responsible for ensuring the validity of this test method for water samples of untested matrices.
An annex gives indications on the necessary counting conditions to meet the required sensitivity for drinking water monitoring.
|
Published |
2013-09 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-3:2013 |
Water quality — Radon-222 — Part 3: Test method using emanometry |
ISO 13164-3:2013 specifies a test method for the determination of radon-222 activity concentration in a sample of water following its transfer from the aqueous phase to the air phase by degassing and its detection. It gives recommendations for rapid measurements performed within less than 1 h.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, range from 0,1 Bq l−1 to several hundred thousand becquerels per litre for a 100 ml test sample.
This test method is used successfully with drinking water samples. The laboratory is responsible for ensuring the validity of this test method for water samples of untested matrices.
This test method can be applied on field sites or in the laboratory.
Annexes A and B give indications on the necessary counting conditions to meet the required sensitivity for drinking water monitoring
|
Published |
2013-09 |
Edition : 1 |
Number of pages : 23 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-4:2015 |
Water quality — Radon-222 — Part 4: Test method using two-phase liquid scintillation counting |
ISO 13164-4:2015 describes a test method for the determination of radon-222 (222Rn) activity concentration in non-saline waters by extraction and liquid scintillation counting.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, are at least above 0,5 Bq l−1 for a 10 ml test sample and a measuring time of 1 h.
This test method can be used successfully with drinking water samples and it is the responsibility of the laboratory to ensure the validity of this test method for water samples of untested matrices.
Annex A gives indication on the necessary counting conditions to meet the required detection limits for drinking water monitoring.
|
Published |
2015-06 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 21909:2005/Cor 1:2007 |
Passive personal neutron dosemeters — Performance and test requirements — Technical Corrigendum 1 |
|
Withdrawn |
2007-10 |
Edition : 1 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO/FDIS 13164-4 |
Water quality — Radon-222 — Part 4: Test method using two-phase liquid scintillation counting |
ISO 13164-4:2015 describes a test method for the determination of radon-222 (222Rn) activity concentration in non-saline waters by extraction and liquid scintillation counting.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, are at least above 0,5 Bq l−1 for a 10 ml test sample and a measuring time of 1 h.
This test method can be used successfully with drinking water samples and it is the responsibility of the laboratory to ensure the validity of this test method for water samples of untested matrices.
Annex A gives indication on the necessary counting conditions to meet the required detection limits for drinking water monitoring.
|
Under development |
|
Edition : 2 |
Number of pages : 16 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13166:2014 |
Water quality — Uranium isotopes — Test method using alpha-spectrometry |
ISO 13166:2014 specifies the conditions for the determination of uranium isotope activity concentration in samples of environmental water (including sea waters) using alpha-spectrometry and 232U as a yield tracer. A chemical separation is required to separate and purify uranium from a test portion of the sample.
Plutonium isotopes can interfere, if present, with detectable activities in the sample.
The detection limit for measurement of a test portion of about 500 ml is approximately 5 mBq · l−1 with a counting time of about 200 000 s.
|
Withdrawn |
2014-03 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 13166:2020 |
Water quality — Uranium isotopes — Test method using alpha-spectrometry |
This document specifies the conditions for the determination of uranium isotope activity concentration in samples of environmental water (including sea waters) using alpha-spectrometry and 232U as a yield tracer.
A chemical separation is required to separate and purify uranium from a test portion of the sample.
|
Published |
2020-08 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO/FDIS 13167 |
Water quality — Plutonium, americium, curium and neptunium — Test method using alpha spectrometry |
ISO 13167:2015 specifies a test method for measuring actinides (238Pu, 239+240Pu, 241Am, 242Cm, 243+244Cm and 237Np) in water samples by alpha spectrometry following a chemical separation.
The method can be used for any type of environmental study or monitoring.
The volume of the test portion required depends on the assumed activity of the sample and the desired detection limit.
The detection limit of the test method is 5 × 10−3 to 5 × 10−4 Bq/l for a volume of the test portion of 0,1 l to 5 l with a counting time of two to ten days.
|
Under development |
|
Edition : 2 |
Number of pages : 29 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13168:2015 |
Water quality — Simultaneous determination of tritium and carbon 14 activities — Test method using liquid scintillation counting |
ISO 13168:2015 describes a test method for the simultaneous measurement of tritium and carbon-14 in water samples by liquid scintillation counting of a source obtained by mixing the water sample with a hydrophilic scintillation cocktail.
This is considered a screening method because of the potential presence of interfering nuclides in the test sample.
The method can be used for any type of environmental study or monitoring.
ISO 13168:2015 is applicable to all types of waters having an activity concentration ranging from 5 Bq/l to 106 Bq/l (upper limit of the liquid scintillation counters for direct counting). For higher activity concentrations, the sample can be diluted to obtain a test sample within this range.
|
Published |
2015-07 |
Edition : 1 |
Number of pages : 16 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO/DIS 13168 |
Water quality — Simultaneous determination of tritium and carbon 14 activities — Test method using liquid scintillation counting |
|
Under development |
|
Edition : 2 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 13304-1:2013 |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 1: General principles |
The primary purpose of ISO 13304-1:2013 is to provide minimum acceptable criteria required to establish procedure of retrospective dosimetry by electron paramagnetic resonance spectroscopy and to report the results.
The second purpose is to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories.
ISO 13304-1:2013 covers the determination of absorbed dose in the measured material. It does not cover the calculation of dose to organs or to the body. It covers measurements in both biological and inanimate samples, and specifically:
based on inanimate environmental materials, usually made at X-band microwave frequencies (8 GHz to 12 GHz);
in vitro tooth enamel using concentrated enamel in a sample tube, usually employing X-band frequency, but higher frequencies are also being considered;
in vivo tooth dosimetry, currently using L-band (1 GHz to 2 GHz), but higher frequencies are also being considered;
in vitro nail dosimetry using nail clippings measured principally at X-band, but higher frequencies are also being considered;
in vivo nail dosimetry with the measurements made at X-band on the intact finger or toe;
in vitro measurements of bone, usually employing X-band frequency, but higher frequencies are also being considered.
For the biological samples, the in vitro measurements are carried out in samples after their removal from the person and under laboratory conditions, whereas the measurements in vivo may take place under field conditions.
NOTE The dose referred to in ISO 13304-1:2013 is the absorbed dose of ionizing radiation in the measured materials.
|
Withdrawn |
2013-07 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 13304-1:2020 |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 1: General principles |
The primary purpose of this document is to provide minimum acceptable criteria required to establish a procedure for retrospective dosimetry by electron paramagnetic resonance spectroscopy and to report the results.
The second purpose is to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories.
This document covers the determination of absorbed dose in the measured material. It does not cover the calculation of dose to organs or to the body. It covers measurements in both biological and inanimate samples, and specifically:
a) based on inanimate environmental materials like glass, plastics, clothing fabrics, saccharides, etc., usually made at X-band microwave frequencies (8 GHz to 12 GHz);
b) in vitro tooth enamel using concentrated enamel in a sample tube, usually employing X-band frequency, but higher frequencies are also being considered;
c) in vivo tooth dosimetry, currently using L-band (1 GHz to 2 GHz), but higher frequencies are also being considered;
d) in vitro nail dosimetry using nail clippings measured principally at X-band, but higher frequencies are also being considered;
e) in vivo nail dosimetry with the measurements made at X-band on the intact finger or toe;
f) in vitro measurements of bone, usually employing X-band frequency, but higher frequencies are also being considered.
For biological samples, in vitro measurements are carried out in samples after their removal from the person or animal and under laboratory conditions, whereas the measurements in vivo are carried out without sample removal and may take place under field conditions.
NOTE The dose referred to in this document is the absorbed dose of ionizing radiation in the measured materials.
|
Published |
2020-07 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 13304-2:2020 |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 2: Ex vivo human tooth enamel dosimetry |
The purpose of this document is to provide minimum criteria required for quality assurance and quality control, evaluation of the performance and to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories applying ex vivo X-band EPR spectroscopy with human tooth enamel.
This document covers the determination of absorbed dose in tooth enamel (hydroxyapatite). It does not cover the calculation of dose to organs or to the body.
This document addresses:
a) responsibilities of the customer and laboratory;
b) confidentiality and ethical considerations;
c) laboratory safety requirements;
d) the measurement apparatus;
e) preparation of samples;
f) measurement of samples and EPR signal evaluation;
g) calibration of EPR dose response;
h) dose uncertainty and performance test;
i) quality assurance and control.
|
Published |
2020-07 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 14146:2000 |
Radiation protection — Criteria and performance limits for the periodic evaluation of processors of personal dosemeters for X and gamma radiation |
|
Withdrawn |
2000-06 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
13.280
Radiation protection
|
| ISO 14146:2018 |
Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services |
The quality of a supplier of a dosimetry service depends on both the characteristics of the approved (type‑tested) dosimetry system[1] and the training and experience of the staff, together with the calibration procedures and quality assurance programmes.
This document specifies the criteria and the test procedures to be used for the periodic verification of the performance of dosimetry services supplying personal and/or area dosemeters.
An area dosemeter can be a workplace dosemeter or an environmental dosemeter.
The performance evaluation can be carried out as a part of the approval procedure for a dosimetry system or as an independent check to verify that a dosimetry service fulfils specified national or international type test performance requirements under representative exposure conditions that are expected or mimic workplace fields from the radiological activities being monitored.
This document applies to personal and area dosemeters for the assessment of external photon radiation with a (fluence weighted) mean energy between 8 keV and 10 MeV, beta radiation with a (fluence weighted) mean energy between 60 keV and 1,2 MeV, and neutron radiation with a (fluence weighted) mean energy between 25,3 meV (i.e. thermal neutrons with a Maxwellian energy distribution with kT = 25,3 meV) and 200 MeV.
It covers all types of personal and area dosemeters needing laboratory processing (e.g. thermoluminescent, optically stimulated luminescence, radiophotoluminescent, track detectors or photographic-film dosemeters) and involving continuous measurements or measurements repeated regularly at fixed time intervals (e.g. several weeks, one month).
Active dosemeters (for dose measurement) may also be treated according to this document. Then, they should be treated as if they were passive (i.e. the dosimetry service reads their indicated values and reports them to the evaluation organization).
[1] If this document is applied to a dosimetry system for which no approval (pattern or type test) has been provided, then in the following text approval or type test should be read as the technical data sheet provided by the manufacturer or as the data sheet required by the regulatory authority.
|
Published |
2018-07 |
Edition : 2 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
|
| ISO/CD 14146 |
Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services |
The quality of a supplier of a dosimetry service depends on both the characteristics of the approved (type‑tested) dosimetry system[1] and the training and experience of the staff, together with the calibration procedures and quality assurance programmes.
This document specifies the criteria and the test procedures to be used for the periodic verification of the performance of dosimetry services supplying personal and/or area dosemeters.
An area dosemeter can be a workplace dosemeter or an environmental dosemeter.
The performance evaluation can be carried out as a part of the approval procedure for a dosimetry system or as an independent check to verify that a dosimetry service fulfils specified national or international type test performance requirements under representative exposure conditions that are expected or mimic workplace fields from the radiological activities being monitored.
This document applies to personal and area dosemeters for the assessment of external photon radiation with a (fluence weighted) mean energy between 8 keV and 10 MeV, beta radiation with a (fluence weighted) mean energy between 60 keV and 1,2 MeV, and neutron radiation with a (fluence weighted) mean energy between 25,3 meV (i.e. thermal neutrons with a Maxwellian energy distribution with kT = 25,3 meV) and 200 MeV.
It covers all types of personal and area dosemeters needing laboratory processing (e.g. thermoluminescent, optically stimulated luminescence, radiophotoluminescent, track detectors or photographic-film dosemeters) and involving continuous measurements or measurements repeated regularly at fixed time intervals (e.g. several weeks, one month).
Active dosemeters (for dose measurement) may also be treated according to this document. Then, they should be treated as if they were passive (i.e. the dosimetry service reads their indicated values and reports them to the evaluation organization).
[1] If this document is applied to a dosimetry system for which no approval (pattern or type test) has been provided, then in the following text approval or type test should be read as the technical data sheet provided by the manufacturer or as the data sheet required by the regulatory authority.
|
Under development |
|
Edition : 3 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 22017:2020 |
Water quality — Guidance for rapid radioactivity measurements in nuclear or radiological emergency situation |
This document provides guidelines for testing laboratories wanting to use rapid test methods on water samples that may be contaminated following a nuclear or radiological emergency incident. In an emergency situation, consideration should be given to:
— taking into account the specific context for the tests to be performed, e.g. a potentially high level of contamination;
— using or adjusting, when possible, radioactivity test methods implemented during routine situations to obtain a result rapidly or, for tests not performed routinely, applying specific rapid test methods previously validated by the laboratory, e.g. for 89Sr determination;
— preparing the test laboratory to measure a large number of potentially contaminated samples.
The aim of this document is to ensure decision makers have reliable results needed to take actions quickly and minimize the radiation dose to the public.
Measurements are performed in order to minimize the risk to the public by checking the quality of water supplies. For emergency situations, test results are often compared to operational intervention levels.
NOTE Operational intervention levels (OILs) are derived from IAEA Safety Standards[8] or national authorities[9].
A key element of rapid analysis can be the use of routine methods but with a reduced turnaround time. The goal of these rapid measurements is often to check for unusual radioactivity levels in the test sample, to identify the radionuclides present and their activity concentration levels and to establish compliance of the water with intervention levels[10][11][12]. It should be noted that in such circumstances, validation parameters evaluated for routine use (e.g. reproducibility, precision, etc.) may not be applicable to the modified rapid method. However, due to the circumstances arising after an emergency, the modified method may still be fit-for-purpose although uncertainties associated with the test results need to be evaluated and may increase from routine analyses.
The first steps of the analytical approach are usually screening methods based on gross alpha and gross beta test methods (adaptation of ISO 10704 and ISO 11704) and gamma spectrometry (adaptation of ISO 20042, ISO 10703 and ISO 19581). Then, if required[13], test method standards for specific radionuclides (see Clause 2) are adapted and applied (for example, 90Sr measurement according to ISO 13160) as proposed in Annex A.
This document refers to published ISO documents. When appropriate, this document also refers to national standards or other publicly available documents.
Screening techniques that can be carried out directly in the field are not part of this document.
|
Published |
2020-08 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 14152:2001 |
Neutron radiation protection shielding — Design principles and considerations for the choice of appropriate materials |
This International Standard presents the general methodology governing the design of neutron radiation protection
shielding and the choice of neutron radiation protection shielding materials.
This International Standard is applicable to facilities and operations where neutron sources are located and used,
and where workers are occupationally exposed. These operations and facilities vary considerably in design and
purpose. These facilities and operations include, but are not limited to:
nuclear power plants;
research reactors;
particle accelerators and neutron generators;
fusion research facilities;
transportation packaging for radioactive materials operations;
medical treatment and research facilities and applications;
industrial applications such as use of devices for measuring and detecting moisture and density level;
space applications;
calibration facilities;
radiographic installations;
nuclear fuel cycle installations (reprocessing plants, plutonium solution handling facilities, shielded cells, waste
storage, etc.).
The criteria for the design of neutron shielding and the choice of shielding materials contained in this International
Standard should be applied to the design of neutron radiation protection shielding systems in such facilities.
|
Published |
2001-12 |
Edition : 1 |
Number of pages : 75 |
Technical Committee |
13.280
Radiation protection
|
| ISO 14152:2001/Cor 1:2002 |
Neutron radiation protection shielding — Design principles and considerations for the choice of appropriate materials — Technical Corrigendum 1 |
|
Published |
2002-05 |
Edition : 1 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 15080:2001 |
Nuclear facilities — Ventilation penetrations for shielded enclosures |
|
Published |
2001-09 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 15080:2001/Amd 1:2019 |
Nuclear facilities — Ventilation penetrations for shielded enclosures — Amendment 1 |
|
Published |
2019-05 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 15382:2002 |
Nuclear energy — Radiationprotection — Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation |
This International Standard specifies a procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation and describes the procedure in radiation protection monitoring for external exposure to weakly penetrating radiation in nuclear installations. This radiation comprises beta-minus radiation, beta-plus radiation and conversion electron radiation as well as photon radiation with energies below 15 keV. This International Standard describes the procedure in radiation protection planning and monitoring as well as the measurement and analysis to be applied. It applies to regular nuclear power plant operation including maintenance, waste handling and decommissioning.
The recommendations of this International Standard may also be transferred to other nuclear fields including reprocessing, if the area-specific issues are considered. This International Standard may also be applied to radiation protection at accelerator facilities and in nuclear medicine, biology and research facilities.
|
Withdrawn |
2002-04 |
Edition : 1 |
Number of pages : 24 |
Technical Committee |
13.280
Radiation protection
|
| ISO 15382:2015 |
Radiological protection — Procedures for monitoring the dose to the lens of the eye, the skin and the extremities |
ISO 15382:2015 provides procedures for monitoring the dose to the skin, the extremities, and the lens of the eye. It gives guidance on how to decide if such dosemeters are needed and to ensure that individual monitoring is appropriate to the nature of the exposure, taking practical considerations into account. National regulations, if they exist, provide requirements that need to be followed.
ISO 15382:2015 specifies procedures for individual monitoring of radiation exposure of the skin, extremities (hands, fingers, wrists, forearms, feet and ankles), and lens of the eye in planned exposure situations. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV and electrons and positrons in the range of 60 keV to 10 MeV.
ISO 15382:2015 gives guidance for the design of a monitoring program to ensure compliance with legal individual dose limits. It refers to the appropriate operational dose quantities, and it gives guidance on the type and frequency of individual monitoring and the type and positioning of the dosemeter. Finally, different approaches to assess and analyse skin, extremity, and lens of the eye doses are given.
It is not in the scope of this International Standard to consider exposure due to alpha or neutron radiation fields.
|
Published |
2015-12 |
Edition : 2 |
Number of pages : 27 |
Technical Committee |
13.280
Radiation protection
|
| ISO 15690:2013 |
Radiological protection — Recommendations for dealing with discrepancies between personal dosimeter systems used in parallel |
ISO 15690:2013 provides recommendations for dealing with discrepancies between dosimeter systems used in parallel, in order to comply with established criteria and national regulations.
ISO 15690:2013 gives guidelines for investigating and analysing the discrepancies between the results of personal dosimetry systems, using two or more dosimeters (often one passive dosimeter and one active dosimeter), worn in parallel by the same worker.
ISO 15690:2013 identifies when the difference between measurements made by personal dosimetry systems used in parallel is considered significant and, hence, needs to be investigated.
It specifies the treatment of this difference.
In ISO 15690:2013, only the personal dose equivalent, Hp(10), from photon radiation is considered. Exposure to beta particles and neutrons might need to be taken into account when identified discrepancies are investigated.
ISO 15690:2013 applies to situations where the period of wearing can be integrated to the same period of time for both systems.
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Published |
2013-06 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
13.280
Radiation protection
|
| ISO 16637:2016 |
Radiological protection — Monitoring and internal dosimetry for staff members exposed to medical radionuclides as unsealed sources |
ISO 16637:2016 specifies the minimum requirements for the design of professional programmes to monitor workers exposed to the risk of internal contamination via inhalation by the use of radionuclides as unsealed sources in nuclear medicine imaging and therapy departments. It establishes principles for the development of compatible goals and requirements for monitoring programmes and, when adequate, dose assessment. It presents procedures and assumptions for the risk analysis, for the monitoring programmes, and for the standardized interpretation of monitoring data.
ISO 16637:2016 addresses the following items:
a) purposes of monitoring and monitoring programmes;
b) description of the different categories of monitoring programmes;
c) quantitative criteria for conducting monitoring programmes;
d) suitable methods for monitoring and criteria for their selection;
e) information that has to be collected for the design of a monitoring programme;
f) general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties);
g) frequencies of measurements;
h) procedures for dose assessment based on reference levels for routine and special monitoring programmes;
i) assumptions for the selection of dose-critical parameter values;
j) criteria for determining the significance of individual monitoring results;
k) interpretation of workplace monitoring results;
l) uncertainties arising from dose assessments and interpretation of bioassays data;
m) reporting/documentation;
n) quality assurance.
ISO 16637:2016 does not address the following:
- monitoring and internal dosimetry for the workers exposed to laboratory use of radionuclides such as radioimmunoassay techniques;
- monitoring and internal dosimetry for the workers involved in the operation, maintenance, and servicing of PET cyclotrons;
- detailed descriptions of measuring methods and techniques;
- dosimetry for litigation cases;
- modelling for the improvement of internal dosimetry;
- the potential influence of medical treatment of the internal contamination;
- the investigation of the causes or implications of an exposure;
- dosimetry for ingestion exposures and for contaminated wounds.
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Published |
2016-02 |
Edition : 1 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
|
| ISO 16639:2017 |
Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities |
ISO 16639:2017 provides guidelines and performance criteria for sampling airborne radioactive substances in the workplace. Emphasis is on health protection of workers in the indoor environment.
ISO 16639:2017 provides best practices and performance-based criteria for the use of air sampling devices and systems, including retrospective samplers and continuous air monitors. Specifically, this document covers air sampling program objectives, design of air sampling and monitoring programs to meet program objectives, methods for air sampling and monitoring in the workplace, and quality assurance to ensure system performance toward protecting workers against unnecessary inhalation exposures.
The primary purpose of the surveillance of airborne activity concentrations in the workplace is to evaluate and mitigate inhalation hazards to workers in facilities where these can become airborne. A comprehensive surveillance program can be used to
- determine the effectiveness of administrative and engineering controls for confinement,
- measure activity concentrations of radioactive substances,
- alert workers to high activity concentrations in the air,
- aid in estimating worker intakes when bioassay methods are unavailable,
- determine signage or posting requirements for radiation protection, and
- determine appropriate protective equipment and measures.
Air sampling techniques consist of two general approaches. The first approach is retrospective sampling, in which the air is sampled, the collection medium is removed and taken to a radiation detector system and analysed for radioactive substance, and the concentration results made available at a later time. In this context, the measured air concentrations are evaluated retrospectively. The second approach is continuous real-time air monitoring so that workers can be warned that a significant release of airborne radioactivity may have just occurred. In implementing an effective air sampling program, it is important to achieve a balance between the two general approaches. The specific balance depends on hazard level of the work and the characteristics of each facility.
A special component of the second approach which can apply, if properly implemented, is the preparation of continuous air monitoring instrumentation and protocols. This enables radiation protection monitoring of personnel that have been trained and fitted with personal protective equipment (PPE) that permit pre-planned, defined, extended stay time in elevated concentrations of airborne radioactive substances. Such approaches can occur either as part of a planned re-entry of a contaminated area following an accidental loss of containment for accident assessment and recovery, or part of a project which involves systematic or routine access to radioactive substances (e.g. preparing process material containing easily aerosolized components), or handling objects such as poorly characterized waste materials that may contain radioactive contaminants that could be aerosolized when handled during repackaging. In this special case, the role of continuous air monitoring is to provide an alert to health physics personnel that the air concentrations of concern have exceeded a threshold such that the planned level of protection afforded by PPE has been or could be exceeded. This level would typically be many 10's or 100's of times higher than the derived air concentration (DAC) established for unprotected workers. The monitoring alarm or alert would therefore be designed not to be confused with the normal monitoring alarm, and the action taken in response would be similarly targeted at the specific site and personnel involved.
The air sampling strategy should be designed to minimize internal exposures and balanced with social, technical, economic, practical, and public policy considerations that are associated with the use of the radioactive substance.
A comprehensive air sampling strategy should also consider that the air sampling program is only one element of a broader radiation protection program. Therefore, individuals involved with the air sampling program should interact with personnel working in other elements of the radiation protection program, such as contamination control and internal dosimetry.
ISO 16639:2017 does not address outdoor air sampling, effluent monitoring, or radon measurements.
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Published |
2017-01 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
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| ISO 16640:2021 |
Monitoring radioactive gases in effluents from facilities producing positron emitting radionuclides and radiopharmaceuticals |
This document focuses on monitoring the activity concentrations of radioactive gases. They allow the calculation of the activity releases, in the gaseous effluent discharge from facilities producing positron emitting radionuclides and radiopharmaceuticals. Such facilities produce short-lived radionuclides used for medical purposes or research and can release gases typically including, but not limited to 18F, 11C, 15O and 13N. These facilities include accelerators, radiopharmacies, hospitals and universities. This document provides performance‑based criteria for the design and use of air monitoring equipment including probes, transport lines, sample monitoring instruments, and gas flow measuring methods. This document also provides information on monitoring program objectives, quality assurance, development of air monitoring control action levels, system optimisation and system performance verification.
The goal of achieving an unbiased measurement is accomplished either by direct (in-line) measurement on the exhaust stream or with samples extracted from the exhaust stream (bypass), provided that the radioactive gases are well mixed in the airstream. This document sets forth performance criteria and recommendations to assist in obtaining valid measurements.
NOTE 1 The criteria and recommendations of this document are aimed at monitoring which is conducted for regulatory compliance and system control. If existing air monitoring systems were not designed according to the performance criteria and recommendations of this document, an evaluation of the performance of the system is advised. If deficiencies are discovered based on a performance evaluation, a determination of the need for a system retrofit is to be made and corrective actions adopted where practicable.
NOTE 2 The criteria and recommendations of this document apply under both normal and off‑normal operating conditions, provided that these conditions do not include production of aerosols or vapours. If the normal and/or off-normal conditions produce aerosols and vapours, then the aerosol collection principles of ISO 2889 also apply.
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Published |
2021-01 |
Edition : 1 |
Number of pages : 54 |
Technical Committee |
13.280
Radiation protection
;
13.030.30
Special wastes
|
| ISO 16645:2016 |
Radiological protection — Medical electron accelerators — Requirements and recommendations for shielding design and evaluation |
ISO 16645:2016 is applicable to medical electron linear accelerators i.e. linear accelerators with nominal energies of the beam ranging from 4 MV to 30 MV, including particular installations such as robotic arm, helical intensity modulated radiotherapy devices and dedicated devices for intra operative radiotherapy (IORT) with electrons.
The cyclotrons and the synchrotrons used for hadrontherapy are not considered.
The radiation protection requirements and recommendations given in ISO 16645:2016 cover the aspects relating to regulations, shielding design goals and other design criteria, role of the manufacturers, of the radiation protection officer or qualified expert and interactions between stakeholders, radiations around a linear accelerator, shielding for conventional and special devices (including shielding materials and transmission values, calculations for various treatment room configurations, duct impact on radiation protection) and the radiological monitoring (measurements).
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Published |
2016-10 |
Edition : 1 |
Number of pages : 76 |
Technical Committee |
13.280
Radiation protection
|
| ISO/DIS 16646 |
Nuclear installations — Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities |
|
Under development |
|
Edition : 1 |
Number of pages : 77 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 16659-1:2022 |
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 1: General requirements |
The scope of ISO 16659 series is to provide different test methods aiming at assessing the efficiency of radioactive iodine traps in ventilation systems of nuclear facilities. The ISO 16659 series deals with iodine traps containing a solid sorbent — mainly activated and impregnated charcoal, the most common solid iodine sorbents used in the ventilation systems of nuclear facilities — as well as other sorbents for special conditions (e.g. high temperature zeolites).
The scope of this document is to provide general and common requirements for the different test methods for industrial nuclear facilities. The different methods will be described in other specific parts of ISO 16659 series. Nuclear medicine applications are excluded from the scope of ISO 16659 series.
In principle, ISO 16659 series is used mainly for filtering radioactive iodine, but other radioactive gases can also be trapped together with iodine. In such a case, some specificity may have to be adapted for these other radioactive gases in specific parts of ISO 16659 series.
This document describes the main general requirements in order to check in situ the efficiency of the iodine traps, according to test conditions that are proposed to be as reproducible as possible.
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Published |
2022-12 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 17099:2014 |
Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry |
ISO 17099:2014 addresses the following:
a) confidentiality of personal information for the customer and the laboratory;
b) laboratory safety requirements;
c) radiation sources, dose rates, and ranges used for establishing the calibration reference dose-effect curves allowing the dose estimation from CBMN assay yields and the minimum resolvable dose;
d) performance of blood collection, culturing, harvesting, and sample preparation for CBMN assay scoring;
e) scoring criteria;
f) conversion of micronucleus frequency in binucleated cells into an estimate of absorbed dose;
g) reporting of results;
h) quality assurance and quality control;
i) informative annexes containing examples of a questionnaire, instructions for customers, a microscope scoring data sheet, a sample report and advice on strengths and limitations of current automated systems for automated micronucleus scoring.
|
Published |
2014-11 |
Edition : 1 |
Number of pages : 31 |
Technical Committee |
13.280
Radiation protection
|
| ISO/CD 17099 |
Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry |
|
Under development |
|
Edition : 2 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-1:2004 |
Remote handling devices for radioactive materials — Part 1: General requirements |
ISO 17874-1:2004 describes requirements concerning devices for remote handling of radioactive materials.
|
Withdrawn |
2004-04 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-1:2010 |
Remote handling devices for radioactive materials — Part 1: General requirements |
ISO 17874-1:2010 describes requirements concerning devices for remote handling of radioactive materials. The classification of these devices (categories and different designs within a category) and the distribution in the different parts are also given.
|
Published |
2010-01 |
Edition : 2 |
Number of pages : 27 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-2:2004 |
Remote-handling devices for radioactive materials — Part 2: Mechanical master-slave manipulators |
ISO 17874-2:2004 specifies the criteria for the selection, installation and use of a mechanical master-slave manipulator, for remote handling of radiaoactive materials in a nuclear facility.
ISO 17874-2:2004 deals only with the technical aspects related to the manipulator and its interface with the nuclear facility in which it is intended to be installed.
In particular, the process apparatus and the manipulator features need to be studied in parallel in order to optimize all the functionalities of the manipulator.
However, ISO 17874-2:2004 does not cover the fundamental design criteria of the nuclear facility (e.g. the process involved, maintenance of the process equipment, intervention for other purposes).
|
Published |
2004-12 |
Edition : 1 |
Number of pages : 49 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-3:2011 |
Remote handling devices for radioactive materials — Part 3: Electrical master-slave manipulators |
ISO 17874-3:2011 specifies the main features of electrical master-slave manipulators intended to be used for nuclear applications. It outlines basic principles which relate to the design features of electrical master-slave manipulators for applications both inside and outside nuclear plant buildings.
ISO 17874-3:2011 does not address prototypes, experimental devices and obsolete types, involving variations in design which omit one or more essential features of electrical master-slave manipulators (e.g. force reflection).
|
Published |
2011-11 |
Edition : 1 |
Number of pages : 38 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-4:2006 |
Remote handling devices for radioactive materials — Part 4: Power manipulators |
ISO 17874:2006 defines the main features of power manipulators for use in ionizing radiation fields. It outlines basic principles which relate to the design and testing of power manipulators for use behind shielding walls, mainly in hot cells.
|
Published |
2006-01 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-5:2007 |
Remote handling devices for radioactive materials — Part 5: Remote handling tongs |
The purpose of ISO 17874-5:2007 is to provide guidance for the selection, installation and use of manually-operated remote handling tongs within nuclear installations.
ISO 17874-5:2007 covers only the specific engineering aspects of manually-operated remote handling tongs and their interfaces with the nuclear facilities in which these devices are to be installed.
Specifically, ISO 17874-5:2007 does not address design options concerning aspects such as the process and general maintenance arrangements that lead to the selection of any particular type of remote handling device.
|
Published |
2007-02 |
Edition : 1 |
Number of pages : 38 |
Technical Committee |
13.280
Radiation protection
|
| ISO 22127:2019 |
Dosimetry with radiophotoluminescent glass dosimeters for dosimetry audit in MV X-ray radiotherapy |
This document specifies the dose assessment method when an RPLD is used for dosimetry audit in external high-energy X-ray beam radiotherapy.
The dosimetry for electron beams and X-ray beams of stereotactic radiotherapy, gamma‑ray of brachytherapy is not included in this version.
This document addresses RPLD handling, measurement method, conversion of measured value to dose, necessary correction coefficient, and the performance requirements for RPLD systems, including the reader.
|
Published |
2019-12 |
Edition : 1 |
Number of pages : 17 |
Technical Committee |
13.280
Radiation protection
|
| ISO/TS 18090-1:2015 |
Radiological protection — Characteristics of reference pulsed radiation — Part 1: Photon radiation |
ISO/TS 18090-1:2015 is directly applicable to pulsed X-radiation with pulse duration of 0,1 ms up to 10 s. This covers the whole range used in medical diagnostics at the time of publication. Some specifications may also be applicable for much shorter pulses; one example is the air kerma of one pulse. Such a pulse may be produced, e.g. by X-ray flash units or high-intensity femtosecond-lasers. Other specifications are not applicable for much shorter pulses; one example is the time-dependent behaviour of the air kerma rate. This may not be measurable for technical reasons as no suitable instrument is available, e.g. for pulses produced by a femtosecond-laser.
ISO/TS 18090-1:2015 specifies the characteristics of reference pulsed radiation for calibrating and testing radiation protection dosemeters and dose rate meters with respect to their response to pulsed radiation. The radiation characteristics includes the following:
a) time-dependent behaviour of the air kerma rate of the pulse;
b) time-dependent behaviour of the X-ray tube high voltage during the pulse;
c) uniformity of the air kerma rate within a cross-sectional area of the radiation beam;
d) air kerma of one radiation pulse;
e) air kerma rate of the radiation pulse;
f) repetition frequency.
ISO/TS 18090-1:2015 does not define new radiation qualities. Instead, it uses those radiation qualities specified in existing ISO and IEC standards. This part of ISO/TS 18090 gives the link between the parameters for pulsed radiation and the parameters for continuous radiation specifying the radiation qualities. It does not specify specific values or series of values for the pulsed radiation field but specifies only those limits for the relevant pulsed radiation parameters that are required for calibrating dosemeters and dose rate meters and for determining their response depending on the said parameters.
The pulse parameters with respect to the phantom-related quantities were determined using conversion coefficients according to ISO 4037 (all parts). This is possible as the radiation qualities specified in existing ISO and IEC standards are used.
A given reference pulsed X-ray facility is characterized by the parameter ranges over which the full specifications and requirements according to this part of ISO/TS 18090 are met. Therefore, not all reference pulsed X-ray facilities can produce pulses covering the same parameter ranges.
|
Published |
2015-08 |
Edition : 1 |
Number of pages : 17 |
Technical Committee |
13.280
Radiation protection
|
| ISO 18310-1:2017 |
Measurement and prediction of the ambient dose equivalent from patients receiving iodine 131 administration after thyroid ablation — Part 1: During the hospitalization |
ISO 18310-1:2017 specifies suitable methods for the measurement of ambient dose equivalent rate at a distance from the patient treated with radioiodine to ablate the thyroid. For this purpose, direct measurement of the ambient dose equivalent rate due to the inpatients using an ionization chamber (or other suitable devices) may be employed.
ISO 18310-1:2017 addresses the measurement methods, the calibration of ionization chamber and the uncertainty estimation for the measurement of the ambient dose equivalent rate of the patient treated with radioiodine to ablate the thyroid using the ionization chamber.
|
Published |
2017-01 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
13.280
Radiation protection
|
| ISO 18310-2:2021 |
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 |
This document addresses the measurement methods, procedures and uncertainty estimation for the measurement, using a personal dosimeter, of the effective dose to the caregiver in the vicinity of the patient treated with radioiodine to ablate the thyroid.
The general requirements for the patient and caregiver and a guidance (see Annex A) for designated expert on instructing caregivers of discharged patients is considered to effectively measure the effective dose to the caregiver in the vicinity of the patient.
|
Published |
2021-05 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
|
| ISO 18417:2017 |
Iodine charcoal sorbents for nuclear facilities — Method for defining sorption capacity index |
The scope of ISO 18417:2017 covers
- iodine sorbents for nuclear power plants, nuclear facilities, research and other nuclear reactors,
- iodine sorbents for laboratories, including nuclear medicine, and
- iodine sorbents for sampling equipment on sample lines.
ISO 18417:2017 applies to iodine sorbents manufacturers and operators in order to measure the actual performance of these sorbents and their sorption capacity for radioiodine.
ISO 18417:2017 applies to granulated and crushed iodine sorbents based on activated charcoal (hereinafter referred to as "sorbents") used for trapping gaseous radioiodine and its compounds. This document establishes the method and conditions for defining sorption capacity index in a laboratory.
|
Published |
2017-03 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
|
| ISO 19238:2004 |
Radiation protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics |
ISO 19238:2004 provides criteria for quality assurance and quality control, evaluation of the performance and the accreditation of biological dosimetry by cytogenetic service laboratories.
|
Withdrawn |
2004-08 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 19238:2014 |
Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics |
ISO 19238:2014 provides criteria for quality assurance and quality control, evaluation of the performance, and the accreditation of biological dosimetry by cytogenetic service laboratories.
ISO 19238:2014 addresses
a) the confidentiality of personal information, for the customer and the service laboratory,
b) the laboratory safety requirements,
c) the calibration sources and calibration dose ranges useful for establishing the reference dose-effect curves that contribute to the dose estimation from chromosome aberration frequency and the minimum resolvable doses,
d) the scoring procedure for unstable chromosome aberrations used for biological dosimetry,
e) the criteria for converting a measured aberration frequency into an estimate of absorbed dose,
f) the reporting of results,
g) the quality assurance and quality control,
h) informative annexes containing sample instructions for customer, sample questionnaire, sample of report, fitting of the low dose-response curve by the method of maximum likelihood and calculating the error of dose estimate, odds ratio method for cases of suspected exposure to a low dose, and sample data sheet for recording aberrations.
|
Published |
2014-02 |
Edition : 2 |
Number of pages : 29 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 14122-2:2001/Amd 1:2010 |
Safety of machinery — Permanent means of access to machinery — Part 2: Working platforms and walkways — Amendment 1 |
|
Withdrawn |
2010-04 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
13.110
Safety of machinery
|
| ISO 19461-1:2018 |
Radiological protection — Measurement for the clearance of waste contaminated with radioisotopes for medical application — Part 1: Measurement of radioactivity |
This document establishes a method for radioactivity measurement and determination of the storage periods of the radioactive wastes produced as a result of the medical application of radioisotopes based on counting measurements using a detector and decay correction of the initial activity concentration of the radioisotopes contained in the waste stream.
It provides a set of controls and measurements for the self-clearance of the radioactive wastes by which the medical facility can be assured of meeting the clearance level.
This document can also be used by testing laboratories or radioactive waste disposal operators.
This document can also be useful for the guidance of the regulatory body.
NOTE Due to the nature of the tests outlined, this document cannot be applied to pure beta emitting nuclides nor to alpha emitting nuclides with low energy gamma rays.
|
Published |
2018-07 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 19461-2:2022 |
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 |
This document addresses aspects of management of solid biomedical radioactive waste from its generation in nuclear medicine facilities to final clearance and disposal, as well as the manner to establish an effective program for biomedical radioactive waste management.
Liquid and gaseous wastes are excluded from the scope of the document, but solid waste includes spent and surplus solutions of radionuclides contained in vials, tubes or syringes. Therefore, this document should be useful for any nuclear medicine facilities dealing with in vivo medical applications of radionuclides and consequently with the waste associated with such applications.
This document provides a list of the main radionuclides used in nuclear medicine facilities and their main physical characteristics, as well as the guidance to write a radioactive waste management program for their sorting, collection, packaging and labelling, radioactivity surveys and decay storage, clearance levels, and transportation, if necessary, until their ultimate disposal or discharge. This document may also be useful as guidance for regulatory bodies.
|
Published |
2022-06 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 20031:2020 |
Radiological protection — Monitoring and dosimetry for internal exposures due to wound contamination with radionuclides |
This document specifies the requirements for personal contamination monitoring and dose assessment following wounds involving radioactive materials. It includes requirements for the direct monitoring at the wound site, monitoring of uptake of radionuclides into the body and assessment of local and systemic doses following the wound event.
It does not address:
— details of monitoring and assessment methods for specific radionuclides;
— monitoring and dose assessment for materials in contact with intact skin or pre-existing wounds, including hot particles;
— therapeutic protocols. However, the responsible entity needs to address the requirements for decontamination and decorporation treatments if appropriate.
|
Published |
2020-02 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
|
| ISO 20042:2019 |
Measurement of radioactivity — Gamma-ray emitting radionuclides — Generic test method using gamma-ray spectrometry |
This document describes the methods for determining the activity in becquerel (Bq) of gamma‑ray emitting radionuclides in test samples by gamma-ray spectrometry. The measurements are carried out in a testing laboratory following proper sample preparation. The test samples can be solid, liquid or gaseous. Applications include:
— routine surveillance of radioactivity released from nuclear installations or from sites discharging enhanced levels of naturally occurring radioactive materials;
— contributing to determining the evolution of radioactivity in the environment;
— investigating accident and incident situations, in order to plan remedial actions and monitor their effectiveness;
— assessment of potentially contaminated waste materials from nuclear decommissioning activities;
— surveillance of radioactive contamination in media such as soils, foodstuffs, potable water, groundwaters, seawater or sewage sludge;
— measurements for estimating the intake (inhalation, ingestion or injection) of activity of gamma-ray emitting radionuclides in the body.
It is assumed that the user of this document has been given information on the composition of the test sample or the site. In some cases, the radionuclides for analysis have also been specified if characteristic limits are needed. It is also assumed that the test sample has been homogenised and is representative of the material under test.
General guidance is included for preparing the samples for measurement. However, some types of sample are to be prepared following the requirements of specific standards referred to in this document. The generic recommendations can also be useful for the measurement of gamma-ray emitters in situ.
This document includes generic advice on equipment selection (see Annex A), detectors (more detailed information is included in Annex D), and commissioning of instrumentation and method validation. Annex F summarises the influence of different measurement parameters on results for a typical gamma-ray spectrometry system. Quality control and routine maintenance are also covered, but electrical testing of the detector and pulse processing electronics is excluded. It is assumed that any data collection and analysis software used has been written and tested in accordance with relevant software standards such as ISO/IEC/IEEE 12207.
Calibration using reference sources and/or numerical methods is covered, including verification of the results. It also covers the procedure to estimate the activity content of the sample (Bq) from the spectrum.
The principles set out in this document are applicable to measurements by gamma-ray spectrometry in testing laboratories and in situ. However, the detailed requirements for in situ measurement are given in ISO 18589-7 and are outside the scope of this document.
This document covers, but is not restricted to, gamma-ray emitters which emit photons in the energy range of 5 keV to 3 000 keV. However, most of the measurements fall into the range 40 keV to 2 000 keV. The activity (Bq) ranges from the low levels (sub-Bq) found in environmental samples to activities found in accident conditions and high level radioactive wastes.
|
Published |
2019-06 |
Edition : 1 |
Number of pages : 50 |
Technical Committee |
13.280
Radiation protection
|
| ISO 20043-1:2021 |
Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 1: Planned and existing exposure situation |
These international guidelines are based on the assumption that monitoring of environmental components (atmosphere, water, soil and biota) as well as food quality ensure the protection of human health[2][4][5][6][7][8]. The guidelines constitute a basis for the setting of national regulations and standards, inter alia, for monitoring air, water and food in support of public health, specifically to protect the public from ionizing radiation.
This document provides
— guidance to collect data needed for the assessment of human exposure to radionuclides naturally present or discharged by anthropogenic activities in the different environmental compartments (atmosphere, waters, soils, biological components) and food;
— guidance on the environmental characterization needed for the prospective and/or retrospective dose assessment methods of public exposure;
— guidance for staff in nuclear installations responsible for the preparation of radiological assessments in support of permit or authorization applications and national authorities' officers in charge of the assessment of doses to the public for the purposes of determining gaseous or liquid effluent radioactive discharge authorizations;
— information for the public on the parameters used to conduct a dose assessment for any exposure situations to a representative person/population. It is important that the dose assessment process be transparent, and that assumptions are clearly understood by stakeholders who can participate in, for example, the selection of habits of the representative person to be considered.
Generic mathematical models used for the assessment of radiological human exposure are presented to identify the parameters to monitor, in order to select, from the set of measurement results, the "best estimates" of these parameter values. More complex models are often used that require the knowledge of supplementary parameters.
The reference and limit values are not included in this document.
|
Published |
2021-01 |
Edition : 1 |
Number of pages : 30 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO/FDIS 20043-2 |
Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 2: Emergency exposure situation |
|
Under development |
|
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO/FDIS 4722-1 |
Water quality — Thorium 232 — Part 1: Test method using alpha spectrometry |
|
Under development |
|
Edition : 1 |
|
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 20046:2019 |
Radiological protection — Performance criteria for laboratories using Fluorescence In Situ Hybridization (FISH) translocation assay for assessment of exposure to ionizing radiation |
The purpose of this document is to provide criteria for quality assurance (QA), quality control (QC) and evaluation of the performance of biological dosimetry by cytogenetic service laboratories.
This document addresses:
a) the responsibilities of both the customer and the laboratory;
b) the confidentiality of personal information, for the customer and the laboratory;
c) the laboratory safety requirements;
d) sample processing; culturing, staining and scoring, including the criteria for scoring for translocation analysis by FISH;
e) the calibration sources and calibration dose ranges useful for establishing the reference dose‑response curves that contribute to the dose estimation from chromosome aberration frequency and the detection limit;
f) the scoring procedure for translocations stained by FISH used for evaluation of exposure;
g) the criteria for converting a measured aberration frequency into an estimate of absorbed dose (also appears as "dose");
h) the reporting of results;
i) the QA and QC;
j) Annexes A to F containing sample instructions for the customer, sample questionnaire, sample datasheet for recording aberrations, sample of report and fitting of the low dose-response curve by the method of maximum likelihood and calculating the uncertainty of dose estimate.
|
Published |
2019-03 |
Edition : 1 |
Number of pages : 41 |
Technical Committee |
13.280
Radiation protection
|
| ISO 20553:2006 |
Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material |
ISO 20553:2006 specifies the minimum requirements for the design of professional programmes to monitor workers exposed to the risk of internal contamination by radioactive substances and establishes principles for the development of compatible goals and requirements for monitoring programmes.
|
Published |
2006-04 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
13.280
Radiation protection
|
| ISO/CD 20553 |
Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material |
|
Under development |
|
Edition : 2 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 20785-1:2006 |
Dosemetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements |
ISO 20785-1:2006 gives the conceptual basis for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft and for the calibration of instruments used for this purpose.
|
Withdrawn |
2006-04 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-1:2012 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements |
ISO 20785:2012 gives the conceptual basis for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft and for the calibration of instruments used for this purpose.
|
Withdrawn |
2012-12 |
Edition : 2 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-1:2020 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements |
This document specifies the conceptual basis for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft and for the calibration of instruments used for that purpose.
|
Published |
2020-07 |
Edition : 3 |
Number of pages : 27 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-2:2011 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 2: Characterization of instrument response |
ISO 20785-1:2011 specifies methods and procedures for characterizing the responses of devices used for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft. The methods and procedures are intended to be understood as minimum requirements.
|
Withdrawn |
2011-06 |
Edition : 1 |
Number of pages : 36 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-2:2020 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 2: Characterization of instrument response |
This document specifies methods and procedures for characterizing the responses of devices used for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft. The methods and procedures are intended to be understood as minimum requirements.
|
Published |
2020-07 |
Edition : 2 |
Number of pages : 36 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO/DIS 4722-2 |
Water quality — Thorium 232 — Part 2: Test method using ICP/MS |
|
Under development |
|
Edition : 1 |
Number of pages : 18 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 20785-3:2015 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes |
The following documents, in whole or in part, are normatively referenced in ISO 20785-3:2015 and are indispensable for its application. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies.
ISO/IEC Guide 98‑1, Uncertainty of measurement ? Part 1: Introduction to the expression of uncertainty in measurement
ISO/IEC Guide 98‑3, Uncertainty of measurement ? Part 3: Guide to the expression of uncertainty in measurement (GUM:1995)
ISO 20785‑1, Dosimetry for exposures to cosmic radiation in civilian aircraft ? Part 1: Conceptual basis for measurements
ISO 20785‑2, Dosimetry for exposures to cosmic radiation in civilian aircraft ? Part 2: Characterization of instrument response
|
Published |
2015-11 |
Edition : 1 |
Number of pages : 16 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO/FDIS 20785-3 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes |
The following documents, in whole or in part, are normatively referenced in ISO 20785-3:2015 and are indispensable for its application. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies.
ISO/IEC Guide 98‑1, Uncertainty of measurement ? Part 1: Introduction to the expression of uncertainty in measurement
ISO/IEC Guide 98‑3, Uncertainty of measurement ? Part 3: Guide to the expression of uncertainty in measurement (GUM:1995)
ISO 20785‑1, Dosimetry for exposures to cosmic radiation in civilian aircraft ? Part 1: Conceptual basis for measurements
ISO 20785‑2, Dosimetry for exposures to cosmic radiation in civilian aircraft ? Part 2: Characterization of instrument response
|
Under development |
|
Edition : 2 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-4:2019 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 4: Validation of codes |
This document is intended for the validation of codes used for the calculation of doses received by individuals on board aircraft. It gives guidance to radiation protection authorities and code developers on the basic functional requirements which the code fulfils.
Depending on any formal approval by a radiation protection authority, additional requirements concerning the software testing can apply.
|
Published |
2019-05 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20899:2018 |
Water quality — Plutonium and neptunium — Test method using ICP-MS |
This document specifies methods used to determine the concentration of plutonium and neptunium isotopes in water by inductively coupled plasma mass spectrometry (ICP-MS) (239Pu, 240Pu, 241Pu and 237Np). The concentrations obtained can be converted into activity concentrations of the different isotopes[9].
Due to its relatively short half-life and 238U isobaric interference, 238Pu can hardly be measured by this method. To quantify this isotope, other techniques can be used (ICP-MS with collision-reaction cell, ICP-MS/MS with collision-reaction cell or chemical separation). Alpha spectrometry measurement, as described in ISO 13167[10], is currently used[11].
This method is applicable to all types of water having a saline load less than 1 g·l−1. A dilution of the sample is possible to obtain a solution having a saline load and activity concentrations compatible with the preparation and the measurement assembly.
A filtration at 0,45 μm is needed for determination of dissolved nuclides. Acidification and chemical separation of the sample are always needed.
The limit of quantification depends on the chemical separation and the performance of the measurement device.
This method covers the measurement of those isotopes in water in activity concentrations between around[12][13]:
— 1 mBq·l−1 to 5 Bq·l−1 for 239Pu, 240Pu and 237Np;
— 1 Bq·l−1 to 5 Bq·l−1 for 241Pu.
In both cases, samples with higher activity concentrations than 5 Bq·l−1 can be measured if a dilution is performed before the chemical separation.
It is possible to measure 241Pu following a pre-concentration step of at least 1 000.
|
Published |
2018-09 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 21243:2008 |
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 |
ISO 21243:2008 is to give an overview of the minimum requirements of process and quality-control components of the cytogenetic response for triage of mass casualties. Cytogenetic triage is the use of chromosome damage to evaluate approximately and rapidly radiation doses received by individuals in order to supplement the early clinical categorization of casualties. ISO 21243:2008 concentrates on organizational aspects of applying the dicentric assay for operation in a triage mode. The technical aspects of the dicentric assay can be found in the ISO 19238, ISO 21243:2008 is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories.
|
Withdrawn |
2008-09 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO/DIS 4723 |
Water quality — Actinium-227 — Test method using alpha-spectrometry |
|
Under development |
|
Edition : 1 |
Number of pages : 25 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 22863-9:2021 |
Fireworks — Test methods for determination of specific chemical substances — Part 9: Mercury content by hydride generation atomic fluorescence spectrometry |
This document specifies the test method for the determination of the mercury content in pyrotechnic compositions by hydride generation atomic fluorescence spectrometry.
|
Published |
2021-02 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
71.100.30
Explosives. Pyrotechnics and fireworks
|
| ISO 21243:2022 |
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 |
The purpose of this document is to give an overview of the minimum requirements for performing the dicentric assay with quality control measures using mitogen stimulated peripheral blood lymphocytes for initial assessment of individuals involved in a mass casualty scenario. The dicentric assay is the use of chromosome damage to quickly estimate approximate radiation doses received by individuals in order to supplement the early clinical categorization of casualties.
This document focuses on the organizational and operational aspects of applying the dicentric assay in an initial assessment mode. The technical aspects of the dicentric assay can be found in ISO 19238.
This document is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories (as defined in Clause 7).
|
Published |
2022-11 |
Edition : 2 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 21482:2007 |
Ionizing-radiation warning — Supplementary symbol |
ISO 21482:2007 specifies the symbol to warn of the presence of a dangerous level of ionizing radiation from a high-level sealed radioactive source that can cause death or serious injury if handled carelessly. This symbol is not intended to replace the basic ionizing radiation symbol (ISO 361), but to supplement it by providing further information on the danger associated with the source and the necessity for untrained or uninformed members of the public to stay away from it.
This symbol is recommended for use with International Atomic Energy Agency (IAEA) Category 1, 2, and 3 sealed radioactive sources. These sources are defined by the IAEA as having the ability to cause death or serious injuries.
|
Published |
2007-02 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
13.280
Radiation protection
;
01.080.20
Graphical symbols for use on specific equipment
|
| ISO 21909-1:2015 |
Passive neutron dosimetry systems — Part 1: Performance and test requirements for personal dosimetry |
ISO 21909-1:2015 provides performance and test requirements for determining the acceptability of neutron dosimetry systems to be used for the measurement of personal dose equivalent, Hp(10), for neutrons ranging in energy from thermal to 20 MeV[1]. No distinction between the different techniques available in the market place is made in the description of the tests. Only generic distinctions, as disposable or reusable dosemeters for instance, are considered. This part of ISO 21909 gives information for extremity dosimetry, based on recommendations given by ICRU Report 66 in Annex A.
[1] This maximal limit of the energy range is only an order of magnitude. The reference radiation fields used for the performance tests are those defined in ISO 8529-1. This means that the maximal energies could only be 14,8 MeV or 19 MeV. The present standard gives performance requirements to 14,8 MeV which is the typical neutron energy encountered for fusion. For fission spectra, the highest energies are around 20 MeV but the contribution to dose equivalent coming from neutrons with energy higher than 14,8 MeV is negligible.
|
Withdrawn |
2015-12 |
Edition : 1 |
Number of pages : 39 |
Technical Committee |
13.280
Radiation protection
|
| ISO 21909-1:2021 |
Passive neutron dosimetry systems — Part 1: Performance and test requirements for personal dosimetry |
This document applies to all passive neutron detectors that can be used within a personal dosemeter in part or in all of the above-mentioned neutron energy range. No distinction between the different techniques available in the marketplace is made in the description of the tests. Only generic distinctions, for instance, as disposable or reusable dosemeters, are considered.
This document describes type tests only. Type tests are made to assess the basic characteristics of the dosimetry systems and are often ensured by recognized national laboratories
This document does not present performance tests for characterizing the degradation induced by the following:
— intrinsic temporal variability of the quality of the dosemeter supplied by the manufacturer;
— intrinsic temporal variability of preparation treatments (before irradiation and/or before reading), if existing;
— intrinsic temporal variability of reading process;
— degradation due to environmental effects on the preparation treatments, if existing;
— degradation due to environmental effects on the reading process.
This document gives information for extremity dosimetry in the Annex C, based on recommendations given by ICRU Report 66. This document addresses only neutron personal monitoring and not criticality accident conditions.
The links between this document and ISO 21909-2 are given in Annex A.
|
Published |
2021-12 |
Edition : 2 |
Number of pages : 42 |
Technical Committee |
13.280
Radiation protection
|
| ISO 21909-2:2021 |
Passive neutron dosimetry systems — Part 2: Methodology and criteria for the qualification of personal dosimetry systems in workplaces |
This document provides methodology and criteria to qualify the dosimetry system at workplaces where it is used. The criteria in this document apply to dosimetry systems which do not meet the criteria with regard to energy and direction dependent responses described in ISO 21909-1.
The qualification of the dosimetry system at workplace aims to demonstrate that:
— either, the non-conformity of the dosimetry system to some of the requirements on the energy or direction dependent responses defined in ISO 21909-1 does not lead to significant discrepancies in the dose determination for a certain workplace field;
— or, that the correction factor or function used for this specific studied workplace enables the dosimetry system to accurately determine the conventional dose value with uncertainties similar to the ones given in ISO 21909-1.
NOTE This document is directed at all stakeholders who are involved: IMSs, accreditation or regulatory bodies, and users of the particular dosimetry (the user is meant as the entity which assigns the dosimetry system to the radiation worker and records the assigned dose.)
The methodologies to characterize the work place field in order to perform the qualification of the dosimetry system are given in Annex A. Annex B is complementary as it gives the practical methods to follow, once one methodology is chosen.
The provider of the dosimetry system shall provide the type test results corresponding to ISO 21909‑1. However, when the dosimetry system to be qualified does not comply with all the criteria of ISO 21909‑1 dealing with the energy and angle dependence of the response, some tests of the ISO 21909-1 can be not performed.
The links between ISO 21909-1 and ISO 21909-2 are described in Annex E.
This document only addresses neutron personal monitoring and not criticality accident conditions.
|
Published |
2021-12 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
|
| ISO 22188:2004 |
Monitoring for inadvertent movement and illicit trafficking of radioactive material |
ISO 22188:2004 specifies methods and means of monitoring for inadvertent movement and illicit trafficking of radioactive material. It provides guidelines on the use of both stationary and portable (e.g. hand-held) instruments to monitor for radiation signatures from radioactive material. Emphasis is placed on the operational aspects, i.e. requirements derived for monitoring of traffic and commodities mainly at border-crossing facilities. Although the term border is used repeatedly in ISO 22188:2004, it is meant to apply not only to international land borders but also maritime ports, airports, and similar locations where goods or individuals are being checked. ISO 22188:2004 does not address the issue of detection of radioactive materials at recycling facilities, although it is recognized that transboundary movement of metals for recycling occurs, and that monitoring of scrap metals may be done at the borders of a state.
ISO 22188:2004 is applicable to regulatory authorities seeking guidance on implementation of action plans to combat illicit trafficking, to law enforcement agencies (e.g. border guards) to obtain guidelines on recommended monitoring procedures, and to equipment manufacturers in order to understand minimum requirements derived from operational necessities according to ISO 22188:2004.
|
Published |
2004-06 |
Edition : 1 |
Number of pages : 35 |
Technical Committee |
13.280
Radiation protection
|
| ISO/FDIS 22188 |
Monitoring for inadvertent movement and illicit trafficking of radioactive material |
|
Under development |
|
Edition : 2 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 22908:2020 |
Water quality — Radium 226 and Radium 228 — Test method using liquid scintillation counting |
This document specifies the determination of radium-226 (226Ra) and radium-228 (228Ra) activity concentrations in drinking water samples by chemical separation of radium and its measurement using liquid scintillation counting.
Massic activity concentrations of 226Ra and 228Ra which can be measured by this test method utilizing currently available liquid scintillation counters go down to 0,01 Bq/kg for 226Ra and 0,06 Bq/kg for 228Ra for a 0,5 kg sample mass and a 1 h counting time in a low background liquid scintillation counter[8].
The test method can be used for the fast detection of contamination of drinking water by radium in emergency situations.
|
Published |
2020-01 |
Edition : 1 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO/TR 22930-1:2020 |
Evaluating the performance of continuous air monitors — Part 1: Air monitors based on accumulation sampling techniques |
The use of a continuous air monitor (CAM) is mainly motivated by the need to be alerted quickly and in the most accurate way possible with an acceptable false alarm rate when a significant activity concentration value is exceeded, in order to take appropriate measures to reduce exposure of those involved.
The performance of this CAM does not only depend on the metrological aspect characterized by the decision threshold, the limit of detection and the measurement uncertainties but also on its dynamic capacity characterized by its response time as well as on the minimum detectable activity concentration corresponding to an acceptable false alarm rate.
The ideal performance is to have a minimum detectable activity concentration as low as possible associated with a very short response time, but unfortunately these two criteria are in opposition. It is therefore important that the CAM and the choice of the adjustment parameters and the alarm levels be in line with the radiation protection objectives.
The knowledge of a few factors is needed to interpret the response of a CAM and to select the appropriate CAM type and its operating parameters.
Among those factors, it is important to know the half-lives of the radionuclides involved, in order to select the appropriate detection system and its associated model of evaluation.
CAM using filter media accumulation sampling techniques are usually of two types:
a) fixed filter;
b) moving filter.
This document first describes the theory of operation of each CAM type i.e.:
— the different models of evaluation considering short or long radionuclides half-lives values,
— the dynamic behaviour and the determination of the response time.
In most case, CAM is used when radionuclides with important radiotoxicities are involved (small value of ALI). Those radionuclides have usually long half-life values.
Then the determination of the characteristic limits (decision threshold, detection limit, limits of the coverage interval) of a CAM is described by the use of long half-life models of evaluation.
Finally, a possible way to determine the minimum detectable activity concentration and the alarms setup is pointed out.
The annexes of this document show actual examples of CAM data which illustrate how to quantify the CAM performance by determining the response time, the characteristics limits, the minimum detectable activity concentration and the alarms setup.
|
Published |
2020-05 |
Edition : 1 |
Number of pages : 52 |
Technical Committee |
13.280
Radiation protection
|
| ISO/TR 22930-2:2020 |
Evaluating the performance of continuous air monitors — Part 2: Air monitors based on flow-through sampling techniques without accumulation |
The use of a continuous air monitor (CAM) is mainly motivated by the need to be alerted quickly and in the most accurate way possible with an acceptable false alarm rate when significant activity concentration value is exceeded, in order to take appropriate measures to reduce exposure of those involved.
The performance of this CAM does not only depend on the metrological aspect characterized by the decision threshold, the limit of detection and the measurement uncertainties but also on its dynamic capacity characterized by its response time as well as on the minimum detectable activity concentration corresponding to an acceptable false alarm rate.
The ideal performance is to have a minimum detectable activity concentration as low as possible associated with a very short response time, but unfortunately these two criteria are in opposition. It is therefore important that the CAM and the choice of the adjustment parameters and the alarm levels be in line with the radiation protection objectives.
This document describes
— the dynamic behaviour and the determination of the response time,
— the determination of the characteristic limits (decision threshold, detection limit, limits of the coverage interval), and
— a possible way to determine the minimum detectable activity concentration and the alarms setup.
Finally the annexes of this document show actual examples of CAM data which illustrate how to quantify the CAM performance by determining the response time, the characteristics limits, the minimum detectable activity concentration and the alarms setup.
|
Published |
2020-05 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
|
| ISO 23018:2022 |
Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors |
This document provides guidance in the preparation, verification, and validation of group-averaged neutron and gamma-ray cross sections for the energy range and materials of importance in radiation protection and shielding calculations for nuclear reactors[1], see also Annex A.
[1] This edition is based on ANSI/ANS-6.1.2-2013[1].
|
Published |
2022-05 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
13.280
Radiation protection
;
27.120.10
Reactor engineering
|
| ISO 5485-2:1980 |
Shipbuilding — Inland vessels — Part 2: Fixed steel deck stairs |
|
Withdrawn |
1980-05 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
47.060
Inland navigation vessels
|
| ISO 23588:2023 |
Radiological protection — General requirements for proficiency tests for in vivo radiobioassay |
This document specifies general requirements for proficiency tests that are offered to in vivo bioassay measurement facilities operating a whole-body counter (WBC) or partial body counter (PBC) for monitoring of persons.
It specifies minimum requirements for proficiency testing applicable to dosimetry laboratories that have dedicated facilities for in vivo monitoring and where accreditation is required as part of providing the service. It also provides general requirements for proficiency testing that may include a larger group of non-accredited laboratories that may perform measurements as part of worker surveillance or in response to an emergency.
This document covers proficiency tests that involve only the quantification of radionuclides and tests that require the identification of radionuclides and their activity.
This document does not define specific requirements on administrative aspects of proficiency testing, such as shipping and finance, that may be the subject of national or international regulation.
|
Published |
2023-02 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
13.280
Radiation protection
|
| ISO/TR 24422:2022 |
Development of a water equivalent phantom to measure the physical characteristics of specific radiosurgery treatment devices |
A water phantom is used to ensure the accurate measurement of absorbed dose delivered by a radiation therapy machine as well as standardizing the dose distribution produced by the radiation therapy device.
This document describes a detailed procedure for the construction and calibration of a polystyrene phantom and the results of its use in measuring the absorbed dose profile around the mechanical centre of a radiosurgery medical device, the full width at half maximum (FWHM) of the field and the physical penumbra at the mechanical centre, as well as the associated uncertainties.
According to IAEA TRS-483 document, the most common design recommended in Gamma Knife® system is a hemisphere atop a water filled or compact polystyrene cylinder, and when using a polystyrene phantom, the measurement depth of the absorbed dose to water is reported to be the centre of the hemisphere with the radius of 8 cm.
This document mainly describes the procedure for measuring the absorbed dose distribution around the mechanical centre of Gamma Knife® and obtaining the FWHM and penumbra from it. The developed phantom is made of polystyrene and has a hemispherical shape in accordance with the design suggested in IAEA TRS-483.
This type of phantom is specific and adapted only for the Gamma Knife® radiosurgery facilities (PerfexionTM and IconTM models) and does not apply to general dosimetry protocols in radiotherapy facilities that use a small radiation field to treat a disease such as LINAC or Cyberknife.
Considering that the type of medical device corresponds to treatment using external beam radiotherapy following small static fields, this technical report follows the recommendations published in the IAEA TRS‑483.
|
Published |
2022-12 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
13.280
Radiation protection
|
| ISO/DIS 24426 |
Radiological protection — Format of input data for the statistical description of dose records of individuals monitored for occupational exposure to ionizing radiation |
|
Under development |
|
Edition : 1 |
Number of pages : 20 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO/CD 24427 |
Radiological protection — Medical proton accelerators — Requirements and recommendations for shielding design and evaluation |
This International Standard is applicable to radiation shielding design and evaluation work for medical proton accelerators with nominal energies of the beam ranging from 70 MeV to 250 MeV, with subsystem such as beamlines, energy selection system (for cyclotron) and nozzle components.
The radiation protection requirements and recommendations given in this international standard cover the aspects relating to regulations, shielding design goals and other design criteria, role of the manufacturers, of the radiation protection officer or qualified expert and interactions between stakeholders, source terms and radiations around a proton accelerator, shielding for accelerators and its subsystems (including shielding materials and transmission values, calculations for various room configurations, duct impact on radiation protection), the radiological monitoring (measurements) and area control.
|
Under development |
|
Edition : 1 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO/DIS 24434-1 |
Radiological protection — Radiological monitoring for emergency workers and population following nuclear/radiological incidents — Part 1: General principles |
|
Under development |
|
Edition : 1 |
Number of pages : 80 |
Technical Committee |
13.100
Occupational safety. Industrial hygiene
;
13.200
Accident and disaster control
;
13.280
Radiation protection
|
| ISO/DIS 24588 |
Protective clothing — Personal protective ensembles for use against chemical, biological, radiological and nuclear (CBRN) agents — Classification, performance requirements and test methods |
|
Under development |
|
Edition : 1 |
Number of pages : 45 |
Technical Committee |
13.280
Radiation protection
;
13.340.10
Protective clothing
|
| ISO 27048:2011 |
Radiation protection — Dose assessment for the monitoring of workers for internal radiation exposure |
ISO 27048:2011 specifies the minimum requirements for the evaluation of data from the monitoring of workers occupationally exposed to the risk of internal contamination by radioactive substances. It presents procedures and assumptions for the standardised interpretation of monitoring data, in order to achieve acceptable levels of reliability. Those procedures allow the quantification of exposures for the documentation of compliance with regulations and radiation protection programmes. Limits are set for the applicability of the procedures in respect of the dose levels above which more sophisticated methods will have to be applied.
ISO 27048:2011 addresses the following: procedures for dose assessment based on reference levels for routine and special monitoring programmes; assumptions for the selection of dose-critical parameter values; criteria for determining the significance of monitoring results; interpretation of workplace monitoring results; uncertainties arising from sampling, measurement techniques and working conditions; the special topics of interpretation of multiple data arising from different measurement methods at different times, handling data below the decision threshold, rogue data, and calculation of doses to the embryo/foetus and infant; reporting/documentation; quality assurance.
It is not applicable to the following: dosimetry for litigation cases; modelling for the improvement of internal dosimetry; the potential influence of decorporation measures (e.g. administration of chelating agents); the investigation of the causes or implications of an exposure; dosimetry for contaminated wounds.
|
Published |
2011-01 |
Edition : 1 |
Number of pages : 76 |
Technical Committee |
13.280
Radiation protection
|
| ISO 28057:2014 |
Dosimetry with solid thermoluminescence detectors for photon and electron radiations in radiotherapy |
ISO 28057:2014 describes rules for the procedures, applications, and systems of thermoluminescence dosimetry (TLD) for dose measurements according to the probe method. It is particularly applicable to solid "TL detectors", i.e. rods, chips, and microcubes, made from LiF:Mg,Ti or LiF:Mg,Cu,P in crystalline or polycrystalline form. The probe method encompasses the arrangement, particularly in a water phantom or in a tissue-equivalent phantom, of single TL detectors or of "TL probes", i.e. sets of TL detectors arranged in thin-walled polymethyl methacrylate (PMMA) casings.
The purpose of these rules is to guarantee the reliability and the accuracy indispensable in clinical dosimetry when applied on or in the patient or phantom. ISO 28057:2014 applies to dosimetry in teletherapy with both photon radiation from 20 keV to 50 MeV and electron radiation from 4 MeV to 25 MeV, as well as in brachytherapy with photon-emitting radionuclides. These applications are complementary to the use of ionization chambers.
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Withdrawn |
2014-03 |
Edition : 1 |
Number of pages : 40 |
Technical Committee |
13.280
Radiation protection
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| ISO 28057:2019 |
Clinical dosimetry — Dosimetry with solid thermoluminescence detectors for photon and electron radiations in radiotherapy |
This document describes rules for the procedures, applications, and systems of thermoluminescence dosimetry (TLD) for dose measurements according to the probe method. It is particularly applicable to solid "TL detectors", i.e. rods, chips, and microcubes, made from LiF:Mg,Ti or LiF:Mg,Cu,P in crystalline or polycrystalline form. It is not applicable to LiF powders because their use requires special procedures. The probe method encompasses the arrangement, particularly in a water phantom or in a tissue-equivalent phantom, of single TL detectors or of "TL probes", i.e. sets of TL detectors arranged in thin-walled polymethyl methacrylate (PMMA) casings.
The purpose of these rules is to guarantee the reliability and the accuracy indispensable in clinical dosimetry when applied on or in the patient or phantom. This document applies to dosimetry in teletherapy with both photon radiation from 20 keV to 50 MeV and electron radiation from 4 MeV to 25 MeV, as well as in brachytherapy with photon-emitting radionuclides. These applications are complementary to the use of ionization chambers.
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Published |
2019-07 |
Edition : 2 |
Number of pages : 41 |
Technical Committee |
13.280
Radiation protection
|