| Name |
Description |
Abstract |
Status |
Publication date |
Edition |
Number of pages |
Technical committee |
ICS |
| 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 13165-1:2013 |
Water quality — Radium-226 — Part 1: Test method using liquid scintillation counting |
ISO 13165-1:2013 specifies the determination of radium-226 (226Ra) activity concentration in non-saline water samples by extraction of its daughter radon-222 (222Rn) and its measurement using liquid scintillation counting.
Radium-226 activity concentrations which can be measured by this test method utilizing currently available liquid scintillation counters goes down to 50 mBq l−1. This method is not applicable to the measurement of other radium isotopes.
|
Withdrawn |
2013-04 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13165-1:2022 |
Water quality — Radium-226 — Part 1: Test method using liquid scintillation counting |
This document specifies the determination of radium-226 (226Ra) activity concentration in non-saline water samples by extraction of its daughter radon-222 (222Rn) and its measurement using liquid scintillation analysis.
The test method described in this document, using currently available scintillation counters, has a detection limit of approximately 50 mBq·l−1. This method is not applicable to the measurement of other radium isotopes.
|
Published |
2022-11 |
Edition : 2 |
Number of pages : 15 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13165-2:2014 |
Water quality — Radium-226 — Part 2: Test method using emanometry |
ISO 13165-2:2014 specifies the determination of radium-226 (226Ra) activity concentration in all types of water by emanometry. The method specified is suitable for the determination of the soluble, suspended, and total 226Ra activity concentration in all types of water with soluble 226Ra activity concentrations greater than 0,02 Bq l−1. In water containing high activity concentrations of 228Th, interference from 220Rn decay products can lead to overestimation of measured levels.
|
Withdrawn |
2014-04 |
Edition : 1 |
Number of pages : 15 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13165-2:2022 |
Water quality — Radium-226 — Part 2: Test method using emanometry |
This document specifies a test method to determine radium-226 (226Ra) activity concentration in all types of water by emanometry.
The test method specified is suitable for the determination of the soluble, suspended and total 226Ra activity concentration in all types of water with soluble 226Ra activity concentrations greater than 0,02 Bq l−1.
The decay chains of 238U and 232Th are given in Annex A. Figure A.1 shows the 238U and its decay chain.
|
Published |
2022-09 |
Edition : 2 |
Number of pages : 16 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13165-3:2016 |
Water quality — Radium-226 — Part 3: Test method using coprecipitation and gamma-spectrometry |
ISO 13165-3:2016 specifies the determination of radium-226 (226Ra) activity concentration in all types of water by coprecipitation followed by gamma-spectrometry (see ISO 18589‑3).
The method described is suitable for determination of soluble 226Ra activity concentrations greater than 0,02 Bq l−1 using a sample volume of 1 l to 100 l of any water type.
For water samples smaller than a volume of 1 l, direct gamma-spectrometry can be performed following ISO 10703 with a higher detection limit.
NOTE This test method also allows other isotopes of radium, 223Ra, 224Ra, and 228Ra, to be determined.
|
Published |
2016-03 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO/DIS 13165-3 |
Water quality — Radium-226 — Part 3: Test method using coprecipitation and gamma-spectrometry |
ISO 13165-3:2016 specifies the determination of radium-226 (226Ra) activity concentration in all types of water by coprecipitation followed by gamma-spectrometry (see ISO 18589‑3).
The method described is suitable for determination of soluble 226Ra activity concentrations greater than 0,02 Bq l−1 using a sample volume of 1 l to 100 l of any water type.
For water samples smaller than a volume of 1 l, direct gamma-spectrometry can be performed following ISO 10703 with a higher detection limit.
NOTE This test method also allows other isotopes of radium, 223Ra, 224Ra, and 228Ra, to be determined.
|
Under development |
|
Edition : 2 |
Number of pages : 15 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13167:2015 |
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.
|
Published |
2015-12 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
;
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 13169:2018 |
Water quality — Uranium — Test method using alpha liquid scintillation counting |
This document specifies the measurement method for the determination of total activity concentration of uranium isotopes in non-saline waters by extraction and liquid scintillation counting.
This method covers the measurement of soluble uranium isotopes in water in activity concentrations between approximately 2·10−3 Bq/kg and 10 Bq/kg when analysing a 1 l test sample volume with a 60 000 s counting time with a typical alpha LSC instrument.
The ratio 234U/238U can also be determined. This method has not been tested for the measurement of other uranium isotopes.
|
Published |
2018-07 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
17.240
Radiation measurements
;
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 14850-1:2004 |
Nuclear energy — Waste-packages activity measurement — Part 1: High-resolution gamma spectrometry in integral mode with open geometry |
ISO 14850:2004 describes a procedure for measurements of gamma-emitting radionuclide activity in homogeneous objects such as unconditioned waste (including process waste, dismantling waste, etc.), waste conditioned in various matrices (bitumen, hydraulic binder, thermosetting resins, etc.), notably in the form of 100 L, 200 L, 400 L or 800 L drums, and test specimens or samples, (vitrified waste), and waste packaged in a container, notably technological waste. It also specifies the calibration of the gamma spectrometry chain. The gamma energies used generally range from 0,05 MeV to 3 MeV.
|
Withdrawn |
2004-05 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
;
13.030.30
Special wastes
|
| ISO 15554:1998 |
Practice for dosimetry in gamma irradiation facilities for food processing |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
|
| ISO 15555:1998 |
Practice for use of a ceric-cerous sulfate dosimetry system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 16638-1:2015 |
Radiological protection — Monitoring and internal dosimetry for specific materials — Part 1: Inhalation of uranium compounds |
ISO 16638-1:2015 specifies the minimum requirements for the design of professional programmes to monitor workers exposed to uranium compounds. It establishes principles for the development of compatible goals and requirements for monitoring programmes and dose assessment for workers occupationally exposed to internal contamination. It establishes procedures and assumptions for risk analysis, monitoring programmes and the standardised interpretation of monitoring data in order to achieve acceptable levels of reliability for uranium and its compounds. It sets limits for the applicability of the procedures in respect to dose levels above which more sophisticated methods have to be applied.
Uranium is both radiologically and chemically toxic. Hence, the scientific bases of current occupational exposure standards are reviewed in addition to radiation exposure limits. This International Standard addresses those circumstances when exposure could be constrained by either radiological or chemical toxicity concerns.
ISO 16638-1:2015 addresses, for uranium and its compounds, 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 monitoring results;
k) interpretation of workplace monitoring results;
l) uncertainties arising from dose assessment and interpretation of bioassays data;
m) reporting/documentation;
n) quality assurance;
o) record keeping requirements.
It is not applicable to the following items:
a) monitoring of exposure due to uranium progeny, including radon;
b) detailed descriptions of measuring methods and techniques for uranium;
c) dosimetry for litigation cases;
d) modelling for the improvement of internal dosimetry;
e) potential influence of counter-measures (e.g. administration of chelating agents);
f) investigation of the causes or implications of an exposure;
g) dosimetry for ingestion exposures and for contaminated wounds.
|
Published |
2015-12 |
Edition : 1 |
Number of pages : 43 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 16638-2:2019 |
Radiological protection — Monitoring and internal dosimetry for specific materials — Part 2: Ingestion of uranium compounds |
This document specifies the minimum requirements for the design of professional programmes to monitor workers exposed to a risk of ingestion to uranium compounds. This document establishes principles for the development of compatible goals and requirements for monitoring programmes and dose assessment for workers occupationally exposed to internal contamination. It establishes procedures and assumptions for risk analysis, monitoring programmes and the standardized interpretation of monitoring data in order to achieve acceptable levels of reliability for uranium and its compounds. It sets limits for the applicability of the procedures in respect to dose levels above which more sophisticated methods need to be applied.
This document addresses those circumstances when exposure could be constrained by either radiological or chemical toxicity concerns.
This document addresses, for ingestion of uranium and its compounds, the following items:
a) purposes of monitoring and monitoring programmes;
b) description of the different categories of monitoring programmes;
c) suitable methods for monitoring and criteria for their selection;
d) information that is collected for the design of a monitoring programme;
e) procedures for dose assessment based on reference levels for special monitoring programmes;
f) criteria for determining the significance of monitoring results;
g) uncertainties arising from dose assessment and interpretation of bioassays data;
h) reporting/documentation;
i) quality assurance;
j) record keeping requirements.
It is not applicable to the following items:
a) detailed descriptions of measuring methods and techniques for uranium;
b) modelling for the improvement of internal dosimetry;
c) potential influence of counter-measures (e.g. administration of chelating agents);
d) investigation of the causes or implications of an exposure;
e) dosimetry for inhalation exposures and for contaminated wounds.
|
Published |
2019-11 |
Edition : 1 |
Number of pages : 27 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 16641:2014 |
Measurement of radioactivity in the environment — Air — Radon 220: Integrated measurement methods for the determination of the average activity concentration using passive solid-state nuclear track detectors |
ISO 16641:2014 covers integrated measurement techniques for radon-220 with passive sampling only. It provides information on measuring the average activity concentration of radon-220 in the air, based on easy-to-use and low-cost passive sampling, and the conditions of use for the measuring devices.
ISO 16641:2014 covers samples taken without interruption over periods varying from a few months to one year.
|
Published |
2014-10 |
Edition : 1 |
Number of pages : 16 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 18589-1:2005 |
Measurement of radioactivity in the environment — Soil — Part 1: General guidelines and definitions |
ISO 18589-1:2005 specifies the general requirements to carry out radionuclides tests on soil sample, including sampling.
ISO 18589-1:2005 is addressed to people responsible for determining the radioactivity present in soils for the purpose of radiation protection. This may concern soils from gardens and farmland, urban or industrial sites, as well as soil not affected by human activities.
ISO 18589-1:2005 is applicable to all laboratories regardless of the number of personnel or the extent of the scope of testing activities. When a laboratory does not undertake one or more of the activities covered by this part of ISO 18589, such as planning, sampling or testing, the requirements of those clauses do not apply.
ISO 18589-1:2005 is to be used in conjunction with other parts of ISO 18589 that outline the setting up of programmes and sampling techniques, methods of general processing of samples in the laboratory and also methods for measuring the radioactivity in soil.
ISO 18589-1:2005 is applicable if radionuclide measurements for the purpose of radiation protection are to be made in following cases:
initial characterization of radioactivity in the environment;routine surveillance of the impact of nuclear installations or of the evolution of the general territory;investigations of accident and incident situations;planning and surveillance of remedial action;decommissioning of installations or clearance of materials.
|
Withdrawn |
2005-05 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-3:2007 |
Measurement of radioactivity in the environment — Soil — Part 3: Measurement of gamma-emitting radionuclides |
ISO 18589-3:2007 specifies the identification and the measurement of the activity in soils of a large number of gamma-emitting radionuclides using gamma spectrometry. This non-destructive method, applicable to large-volume samples (up to about 3 000 cm3), covers the determination in a single measurement of all the g-emitters present for which the photon energy is between 5 keV and 3 MeV.
ISO 18589-3:2007 can be applied by test laboratories performing routine radioactivity measurements as a majority of radionuclides is characterized by gamma-ray emission between 40 keV and 2 MeV.
ISO 18589-3:2007 is suitable for the surveillance of the environment and the inspection of a site and allows, in case of accidents, a quick evaluation of gamma activity.
|
Withdrawn |
2007-12 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-1:2019 |
Measurement of radioactivity in the environment — Soil — Part 1: General guidelines and definitions |
This document specifies the general requirements to carry out radionuclides tests, including sampling of soil including rock from bedrock and ore as well as of construction materials and products, pottery, etc. using NORM or those from technological processes involving Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) e.g. the mining and processing of mineral sands or phosphate fertilizer production and use.
For simplification, the term "soil" used in this document covers the set of elements mentioned above.
This document is addressed to people responsible for determining the radioactivity present in soils for the purpose of radiation protection. This concerns soils from gardens and farmland, urban or industrial sites, as well as soil not affected by human activities.
This document is applicable to all laboratories regardless of the number of personnel or the extent of the scope of testing activities. When a laboratory does not undertake one or more of the activities covered by this document, such as planning, sampling or testing, the requirements of those clauses do not apply.
This document is to be used in conjunction with other parts of ISO 18589 that outline the setting up of programmes and sampling techniques, methods of general processing of samples in the laboratory and also methods for measuring the radioactivity in soil. Its purpose is the following:
— define the main terms relating to soils, sampling, radioactivity and its measurement;
— describe the origins of the radioactivity in soils;
— define the main objectives of the study of radioactivity in soil samples;
— present the principles of studies of soil radioactivity;
— identify the analytical and procedural requirements when measuring radioactivity in soil.
This document is applicable if radionuclide measurements for the purpose of radiation protection are to be made in the following cases:
— initial characterization of radioactivity in the environment;
— routine surveillance of the impact of nuclear installations or of the evolution of the general territory;
— investigations of accident and incident situations;
— planning and surveillance of remedial action;
— decommissioning of installations or clearance of materials.
|
Published |
2019-11 |
Edition : 2 |
Number of pages : 14 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-2:2007 |
Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples |
ISO 18589-2:2007 specifies the general requirements, based on ISO 11074 and ISO/IEC 17025, for all steps in the planning (desk study and area reconnaissance) of the sampling and the preparation of samples for testing. It includes the selection of the sampling strategy, the outline of the sampling plan, the presentation of general sampling methods and equipment, as well as the methodology of the pre-treatment of samples adapted to the measurements of the activity of radionuclides in soil.
ISO 18589-2:2007 is addressed to the people responsible for determining the radioactivity present in soil for the purpose of radiation protection. It is applicable to soil from gardens, farmland, urban or industrial sites, as well as soil not affected by human activities.
ISO 18589-2:2007 is applicable to all laboratories regardless of the number of personnel or the range of the testing performed. When a laboratory does not undertake one or more of the activities covered by ISO 18589-2:2007, such as planning, sampling or testing, the corresponding requirements do not apply.
|
Withdrawn |
2007-12 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-2:2015 |
Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples |
ISO 18589-2:2015 specifies the general requirements, based on ISO 11074 and ISO/IEC 17025, for all steps in the planning (desk study and area reconnaissance) of the sampling and the preparation of samples for testing. It includes the selection of the sampling strategy, the outline of the sampling plan, the presentation of general sampling methods and equipment, as well as the methodology of the pre-treatment of samples adapted to the measurements of the activity of radionuclides in soil.
ISO 18589-2:2015 is addressed to the people responsible for determining the radioactivity present in soil for the purpose of radiation protection. It is applicable to soil from gardens, farmland, urban, or industrial sites, as well as soil not affected by human activities.
ISO 18589-2:2015 is applicable to all laboratories regardless of the number of personnel or the range of the testing performed. When a laboratory does not undertake one or more of the activities covered by this part of ISO 18589, such as planning, sampling, or testing, the corresponding requirements do not apply.
|
Withdrawn |
2015-02 |
Edition : 2 |
Number of pages : 25 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-2:2022 |
Measurement of radioactivity in the environment — Soil — Part 2: Guidance for the selection of the sampling strategy, sampling and pre-treatment of samples |
This document specifies the general requirements, based on ISO 11074 and ISO/IEC 17025, for all steps in the planning (desk study and area reconnaissance) of the sampling and the preparation of samples for testing. It includes the selection of the sampling strategy, the outline of the sampling plan, the presentation of general sampling methods and equipment, as well as the methodology of the pre-treatment of samples adapted to the measurements of the activity of radionuclides in soil including granular materials of mineral origin which contain NORM or artificial radionuclides, such as sludge, sediment, construction debris, solid waste of different type and materials from technologically enhanced naturally occurring radioactive materials (mining, coal combustion, phosphate fertilizer production etc.).
For simplification, the term “soil” used in this document covers the set of elements mentioned above.
This document is addressed to the people responsible for determining the radioactivity present in soil for the purpose of radiation protection. It is applicable to soil from gardens, farmland, urban, or industrial sites, as well as soil not affected by human activities.
This document is applicable to all laboratories regardless of the number of personnel or the range of the testing performed. When a laboratory does not undertake one or more of the activities covered by this document, such as planning, sampling, test or calibration, the corresponding requirements do not apply.
NOTE The term “laboratory” is applicable to all identified entities (individuals, organizations, etc.) performing planning, sampling, test and calibration.
|
Published |
2022-12 |
Edition : 3 |
Number of pages : 28 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO/ASTM 51276:2002 |
Practice for use of a polymethylmethacrylate dosimetry system |
ISO/ASTM 51276 covers procedures for using hermetically-sealed polymethylmethacrylate (PMMA) dosimeters for measuring absorbed doses in materials irradiated by photons or electrons in terms of absorbed dose in water.
It also covers systems that permit absorbed dose measurements under the following conditions:
the absorbed dose range is 0,1 kGy to 100 kGy.
the absorbed dose rate is 1 times 10-2 Gy·s -1 to 1 times 107 Gy·s -1.
the radiation energy range for photons is 0,1 MeV to 50 MeV and for electrons 3 MeV to 50 MeV.
the irradiation temperature is -78 °C to + 50 °C.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 18589-3:2015 |
Measurement of radioactivity in the environment — Soil — Part 3: Test method of gamma-emitting radionuclides using gamma-ray spectrometry |
ISO 18589-3:2015 specifies the identification and the measurement of the activity in soils of a large number of gamma-emitting radionuclides using gamma spectrometry. This non-destructive method, applicable to large-volume samples (up to about 3 000 cm3), covers the determination in a single measurement of all the γ-emitters present for which the photon energy is between 5 keV and 3 MeV.
ISO 18589-3:2015 can be applied by test laboratories performing routine radioactivity measurements as a majority of gamma-emitting radionuclides is characterized by gamma-ray emission between 40 keV and 2 MeV.
The method can be implemented using a germanium or other type of detector with a resolution better than 5 keV.
ISO 18589-3:2015 is addressed to people responsible for determining gamma-emitting radionuclides activity present in soils for the purpose of radiation protection.
|
Published |
2015-02 |
Edition : 2 |
Number of pages : 22 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO/FDIS 18589-3 |
Measurement of radioactivity in the environment — Soil — Part 3: Test method of gamma-emitting radionuclides using gamma-ray spectrometry |
|
Under development |
|
Edition : 3 |
Number of pages : 35 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-4:2009 |
Measurement of radioactivity in the environment — Soil — Part 4: Measurement of plutonium isotopes (plutonium 238 and plutonium 239 + 240) by alpha spectrometry |
ISO 18589-4:2009 describes a method for measuring plutonium 238 and 239 + 240 isotopes in soil by alpha spectrometry samples using chemical separation techniques. The method can be used for any type of environmental study or monitoring. These techniques can also be used for measurements of very low levels of activity, one or two orders of magnitude less than the level of natural alpha-emitting radionuclides.
The mass of the test portion required depends on the assumed activity of the sample and the desired detection limit. In practice, it can range from 0,1 g to 100 g of the test sample.
|
Withdrawn |
2009-03 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-4:2019 |
Measurement of radioactivity in the environment — Soil — Part 4: Plutonium 238 and plutonium 239 + 240 — Test method using alpha spectrometry |
This document describes a method for measuring 238Pu and 239 + 240 isotopes in soil by alpha spectrometry samples using chemical separation techniques.
The method can be used for any type of environmental study or monitoring. These techniques can also be used for measurements of very low levels of activity, one or two orders of magnitude less than the level of natural alpha-emitting radionuclides.
The test methods described in this document can also be used to measure the radionuclides in sludge, sediment, construction material and products following proper sampling procedure[2][3][4][5][7][8].
The mass of the test portion required depends on the assumed activity of the sample and the desired detection limit. In practice, it can range from 0,1 g to 100 g of the test sample.
|
Published |
2019-12 |
Edition : 2 |
Number of pages : 23 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-5:2009 |
Measurement of radioactivity in the environment — Soil — Part 5: Measurement of strontium 90 |
ISO 18589-5:2009 describes the principles for the measurement of the activity of 90Sr in equilibrium with 90Y and 89Sr, pure beta-emitting radionuclides, in soil samples. Different chemical separation methods are presented to produce strontium and yttrium sources, the activity of which is determined using proportional counter (PC) or liquid scintillation counter (LSC). The selection of the measuring method depends on the origin of the contamination, the characteristics of the soil being analysed, the required accuracy of measurement and the resources of the available laboratories.
These methods are used for soil monitoring following past or present, accidental or routine, liquid or gaseous discharges. It also covers the monitoring of contamination caused by global fallout.
In the case of recent fallout immediately following a nuclear accident, the contribution of 89Sr to the total amount of strontium activity is not negligible. ISO 18589-5:2009 provides the measurement method to determine the activity of 90Sr in the presence of 89Sr.
|
Withdrawn |
2009-03 |
Edition : 1 |
Number of pages : 30 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| 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 18589-5:2019 |
Measurement of radioactivity in the environment — Soil — Part 5: Strontium 90 — Test method using proportional counting or liquid scintillation counting |
This document describes the principles for the measurement of the activity of 90Sr in equilibrium with 90Y and 89Sr, pure beta emitting radionuclides, in soil samples. Different chemical separation methods are presented to produce strontium and yttrium sources, the activity of which is determined using proportional counters (PC) or liquid scintillation counters (LSC). 90Sr can be obtained from the test samples when the equilibrium between 90Sr and 90Y is reached or through direct 90Y measurement. The selection of the measuring method depends on the origin of the contamination, the characteristics of the soil to be analysed, the required accuracy of measurement and the resources of the available laboratories.
These methods are used for soil monitoring following discharges, whether past or present, accidental or routine, liquid or gaseous. It also covers the monitoring of contamination caused by global nuclear fallout.
In case of recent fallout immediately following a nuclear accident, the contribution of 89Sr to the total amount of strontium activity will not be negligible. This standard provides the measurement method to determine the activity of 90Sr in presence of 89Sr.
The test methods described in this document can also be used to measure the radionuclides in sludge, sediment, construction material and products by following proper sampling procedure.
Using samples sizes of 20 g and counting times of 1 000 min, detection limits of (0,1 to 0,5) Bq·kg-1 can be achievable for 90Sr using conventional and commercially available proportional counter or liquid scintillation counter when the presence of 89Sr can be neglected. If 89Sr is present in the test sample, detection limits of (1 to 2) Bq·kg-1 can be obtained for both 90Sr and 89Sr using the same sample size, counting time and proportional counter or liquid scintillation counter as in the previous situation.
|
Published |
2019-12 |
Edition : 2 |
Number of pages : 32 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-6:2009 |
Measurement of radioactivity in the environment — Soil — Part 6: Measurement of gross alpha and gross beta activities |
ISO 18589-6:2009 provides a method that allows an estimation of gross radioactivity of alpha- and beta-emitters present in soil samples. ISO 18589-6:2009 applies, essentially, to systematic inspections based on comparative measurements or to preliminary site studies to guide the testing staff both in the choice of soil samples for measurement as a priority and in the specific analysis methods for implementation.
The gross a or β radioactivity is generally different from the sum of the effective radioactivities of the radionuclides present since, by convention, the same alpha counting efficiency is assigned for all the alpha emissions and the same beta counting efficiency is assigned for all the beta emissions
|
Withdrawn |
2009-03 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-6:2019 |
Measurement of radioactivity in the environment — Soil — Part 6: Gross alpha and gross beta activities — Test method using gas-flow proportional counting |
This document provides a method that allows an estimation of gross radioactivity of alpha- and beta-emitters present in soil samples. It applies, essentially, to systematic inspections based on comparative measurements or to preliminary site studies to guide the testing staff both in the choice of soil samples for measurement as a priority and in the specific analysis methods for implementation.
The gross α or β radioactivity is generally different from the sum of the effective radioactivities of the radionuclides present since, by convention, the same alpha counting efficiency is assigned for all the alpha emissions and the same beta counting efficiency is assigned for all the beta emissions.
Soil includes rock from bedrock and ore as well as construction materials and products, potery, etc. using naturally occurring radioactive materials (NORM) or those from technological processes involving Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM), e.g. the mining and processing of mineral sands or phosphate fertilizer production and use.
The test methods described in this document can also be used to assess gross radioactivity of alpha- and beta-emitters in sludge, sediment, construction material and products following proper sampling procedure[2][3][4][5][7][8].
For simplification, the term "soil" used in this document covers the set of elements mentioned above.
|
Published |
2019-12 |
Edition : 2 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology in general
|
| ISO 18589-7:2013 |
Measurement of radioactivity in the environment — Soil — Part 7: In situ measurement of gamma-emitting radionuclides |
ISO 18589-7:2013 specifies the identification of radionuclides and the measurement of their activity in soil using in situ gamma spectrometry with portable systems equipped with germanium or scintillation detectors.
ISO 18589-7:2013 is suitable to rapidly assess the activity of artificial and natural radionuclides deposited on or present in soil layers of large areas of a site under investigation.
ISO 18589-7:2013 can be used in connection with radionuclide measurements of soil samples in the laboratory (ISO 18589‑3) in the following cases:
· routine surveillance of the impact of radioactivity released from nuclear installations or of the evolution of radioactivity in the region;
· investigations of accident and incident situations;
· planning and surveillance of remedial action;
· decommissioning of installations or the clearance of materials.
It can also be used for the identification of airborne artificial radionuclides, when assessing the exposure levels inside buildings or during waste disposal operations.
Following a nuclear accident, in situ gamma spectrometry is a powerful method for rapid evaluation of the gamma activity deposited onto the soil surface as well as the surficial contamination of flat objects.
|
Published |
2013-10 |
Edition : 1 |
Number of pages : 54 |
Technical Committee |
17.240
Radiation measurements
;
13.080.01
Soil quality and pedology 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 19017:2015 |
Guidance for gamma spectrometry measurement of radioactive waste |
ISO 19017:2015 is applicable to gamma radiation measurements on radioactive waste.
Radioactive waste can be found in different forms and exhibit a wide range of characteristics, including the following:
- raw or unconditioned waste, including process waste (filters, resins, control rods, scrap, etc.) and waste from dismantling or decommissioning;
- conditioned waste in various forms and matrices (bitumen, cement, hydraulic binder, etc.);
- very low level (VLLW), low level (LLW), intermediate level (ILW) and high level radioactive waste (HLW);
- different package shapes: cylinders, cubes, parallelepipeds, etc.
Guidance is provided in respect of implementation, calibration, and quality control. The diversity of applications and system realizations (ranging from research to industrial systems, from very low level to high level radioactive waste, from small to large volume packages with different shapes, with different performance requirements and allowable measuring time) renders it impossible to provide specific guidance for all instances; the objective of this International Standard is, therefore, to establish a set of guiding principles. Ultimately, implementation is to be performed by suitably qualified and experienced persons and based on a thorough understanding of the influencing factors, contributing variables and performance requirements of the specific measurement application.
This International Standard assumes that the need for the provision of such a system will have been adequately considered and that its application and performance requirements will have been adequately defined through the use of a structured requirements capture process, such as data quality objectives (DQO).
It is noted that, while outside the scope of this International Standard, many of the principles, measurement methods, and recommended practices discussed here are also equally applicable to gamma measurements of items other than radioactive waste (e.g. bulk food, water, free-standing piles of materials) or to measurements made on radioactive materials contained within non-traditional packages (e.g. in transport containers).
|
Published |
2015-12 |
Edition : 1 |
Number of pages : 48 |
Technical Committee |
17.240
Radiation measurements
;
27.120.30
Fissile materials and nuclear fuel technology
|
| 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/FDIS 19238 |
Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics — The dicentric assay |
|
Under development |
|
Edition : 3 |
|
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 19361:2017 |
Measurement of radioactivity — Determination of beta emitters activities — Test method using liquid scintillation counting |
ISO 19361:2017 applies to liquid scintillation counters and requires the preparation of a scintillation source obtained by mixing the test sample and a scintillation cocktail. The test sample can be liquid (aqueous or organic), or solid (particles or filter or planchet).
ISO 19361:2017describes the conditions for measuring the activity of beta emitter radionuclides by liquid scintillation counting[14][15].
The choice of the test method using liquid scintillation counting involves the consideration of the potential presence of other beta emitter radionuclides in the test sample. In this case, a specific sample treatment by separation or extraction is implemented to isolate the radionuclide of interest in order to avoid any interference with other beta-, alpha- and gamma-emitting radionuclides during the counting phase.
ISO 19361:2017 is applicable to all types of liquid samples having an activity concentration ranging from a few Bq·l−1 to 106 Bq·l−1. For a liquid test sample, it is possible to dilute liquid test samples in order to obtain a solution having an activity compatible with the measuring instrument. For solid samples, the activity of the prepared scintillation source shall be compatible with the measuring instrument.
The measurement range is related to the test method used: nature of test portion, preparation of the scintillator - test portion mixture, measuring assembly as well as to the presence of the co-existing activities due to interfering radionuclides.
Test portion preparations (such as distillation for 3H measurement, or benzene synthesis for 14C measurement, etc.) are outside the scope of this document and are described in specific test methods using liquid scintillation[2][3][4][5][6][7][8][9].
|
Published |
2017-08 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
|
| 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 19581:2017 |
Measurement of radioactivity — Gamma emitting radionuclides — Rapid screening method using scintillation detector gamma-ray spectrometry |
ISO 19581 specifies a screening test method to quantify rapidly the activity concentration of gamma-emitting radionuclides, such as 131I, 132Te, 134Cs and 137Cs, in solid or liquid test samples using gamma-ray spectrometry with lower resolution scintillation detectors as compared with the HPGe detectors (see IEC 61563).
This test method can be used for the measurement of any potentially contaminated environmental matrices (including soil), food and feed samples as well as industrial materials or products that have been properly conditioned. Sample preparation techniques used in the screening method are not specified in ISO 19581, since special sample preparation techniques other than simple machining (cutting, grinding, etc.) should not be required. Although the sampling procedure is of utmost importance in the case of the measurement of radioactivity in samples, it is out of scope of ISO 19581; other international standards for sampling procedures that can be used in combination with ISO 19581 are available (see References [1],[2],[3],[4],[5],[6]).
The test method applies to the measurement of gamma-emitting radionuclides such as 131I, 134Cs and 137Cs. Using sample sizes of 0,5 l to 1,0 l in a Marinelli beaker and a counting time of 5 min to 20 min, decision threshold of 10 Bq·kg−1 can be achievable using a commercially available scintillation spectrometer [e.g. thallium activated sodium iodine (NaI(Tl)) spectrometer 2" ϕ × 2" detector size, 7 % resolution (FWHM) at 662 keV, 30 mm lead shield thickness].
This test method also can be performed in a "makeshift" laboratory or even outside a testing laboratory on samples directly measured in the field where they were collected.
During a nuclear or radiological emergency, this test method enables a rapid measurement of the sample activity concentration of potentially contaminated samples to check against operational intervention levels (OILs) set up by decision makers that would trigger a predetermined emergency response to reduce existing radiation risks[12].
Due to the uncertainty associated with the results obtained with this test method, test samples requiring more accurate test results can be measured using high-purity germanium (HPGe) detectors gamma-ray spectrometry in a testing laboratory, following appropriate preparation of the test samples[7][8].
ISO 19581 does not contain criteria to establish the activity concentration of OILs.
|
Published |
2017-10 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
17.240
Radiation measurements
|
| 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 20044:2022 |
Measurement of radioactivity in the environment — Air: aerosol particles — Test method using sampling by filter media |
This document provides guidance for
— the sampling process of the aerosol particles in the air using filter media. This document takes into account the specific behaviour of aerosol particles in ambient air (Annex B).
— Two methods for sampling procedures with subsequent or simultaneous measurement:
— the determination of the activity concentration of radionuclides bound to aerosol particles in the air knowing the activity deposited in the filter;
— the operating use of continuous air monitoring devices used for real time measurement.
The activity concentration is expressed in becquerel per cubic metre (Bq∙m-3).
This document describes the test method to determine activity concentrations of radionuclides bound to aerosol particles after air sampling passing through a filter media designed to trap aerosol particles. The method can be used for any type of environmental study or monitoring.
The test method is used in the context of a quality assurance management system (ISO/IEC 17025[2]).
This document does not cover the details of measurement test techniques (gamma spectroscopy, global alpha and beta counting, liquid scintillation, alpha spectrometry) used to determine the activity deposited in the media filter, which are either based on existing standards or internal methods developed by the laboratory in charge of those measurements. Also, this document does not cover the variability of the aerosol particle sizes as given by the composition of the dust contained in ambient air[3][4]. This document does not address to sampling of radionuclides bound to aerosol particles in the effluent air of nuclear facilities [see ISO 2889:2021][5].
The procedures described here facilitate the sampling of aerosol bound radionuclides. It is supposed to conform to the national and international requirements for monitoring programmes safety standards of IAEA[6].
The characteristics of the sampling location (coordinates, type of vegetation, obstacles) need to be documented prior to commencing the monitoring. The guidelines of the World Meteorology Organization (WMO) include the criteria for representative measurements of temperature, wind-speed, wind direction, humidity and precipitation for all the weather stations in the world[7].
|
Published |
2022-12 |
Edition : 1 |
Number of pages : 45 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO/FDIS 20045 |
Measurement of the radioactivity in the environment – Air: tritium – Test Method using bubbler sampling |
|
Under development |
|
Edition : 1 |
Number of pages : 35 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO/ASTM 51275:2004 |
Practice for use of a radiochromic film dosimetry system |
ISO/ASTM 51275:2004 covers the procedures for handling, testing and using a radiochromic film dosimetry system to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose in water.
|
Withdrawn |
2004-06 |
Edition : 2 |
Number of pages : 5 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 13091-1:2001 |
Mechanical vibration — Vibrotactile perception thresholds for the assessment of nerve dysfunction — Part 1: Methods of measurement at the fingertips |
|
Published |
2001-05 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.160
Vibration and shock with respect to human beings
|
| 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/DIS 20956 |
Radiological protection — Low dose rate calibration of instruments for environmental and area monitoring |
|
Under development |
|
Edition : 1 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 21439:2009 |
Clinical dosimetry — Beta radiation sources for brachytherapy |
ISO 21439:2009 specifies methods for the determination of absorbed-dose distributions in water or tissue that are required prior to initiating procedures for the application of beta radiation in ophthalmic tumour and intravascular brachytherapy]. Recommendations are given for beta-radiation source calibration, dosemetry measurements, dose calculation, dosemetric quality assurance, as well as for beta-radiation brachytherapy treatment planning. Guidance is also given for estimating the uncertainty of the absorbed dose to water. ISO 21439:2009 is applicable to “sealed” radioactive sources, such as plane and concave surface sources, source trains of single seeds, line sources, shell and volume sources, for which only the beta radiation emitted is of therapeutic relevance.
The standardization of procedures in clinical dosemetry described in ISO 21439:2009 serves as a basis for the reliable application of beta-radiation brachytherapy. The specific dosemetric methods described in ISO 21439:2009 apply to sources for the curative treatment of ophthalmic disease, for intravascular brachytherapy treatment, for overcoming the problem of restenosis and for other clinical applications using beta radiation.
ISO 21439:2009 is geared towards organizations wishing to establish reference methods in dosemetry aiming at clinical demands for an appropriately small uncertainty of the delivered dose. ISO 21439:2009 does not exclude the possibility that there can be other methods leading to the same or smaller measurement uncertainties.
|
Published |
2009-02 |
Edition : 1 |
Number of pages : 92 |
Technical Committee |
17.240
Radiation measurements
;
11.040.50
Radiographic equipment
|
| ISO 21484:2008 |
Nuclear fuel technology — Determination of the O/M ratio in MOX pellets — Gravimetric method |
ISO 21484:2008 describes a method for determining the oxygen-to-metal (O/M) ratio in mixed uranium-plutonium oxide (U,Pu)O2 ± X pellets.
|
Withdrawn |
2008-11 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
17.240
Radiation measurements
;
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 21484:2017 |
Nuclear Energy — Fuel technology — Determination of the O/M ratio in MOX pellets by the gravimetric method |
ISO 21484:2017 describes a method for determining the Oxygen-to-Metal (O/M) ratio in mixed uranium-plutonium oxide (U,Pu)O2 ± X pellets. The parameters given in the following paragraphs are relevant for pellets within a range of O/M ratio corresponding to 1,98 to 2,01. The method described in the document is adapted, with regard to the parameters, if the expected values of O/M ratio are outside the range.
|
Published |
2017-01 |
Edition : 2 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
;
27.120.30
Fissile materials and nuclear fuel technology
|
| 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 22125-1:2019 |
Water quality — Technetium-99 — Part 1: Test method using liquid scintillation counting |
This document specifies a method for the measurement of 99Tc in all types of waters by liquid scintillation counting (LSC).
The method is applicable to test samples of supply/drinking water, rainwater, surface and ground water, as well as cooling water, industrial water, domestic, and industrial wastewater after proper sampling and handling, and test sample preparation. A filtration of the test sample is necessary.
The detection limit depends on the sample volume and the instrument used. The method described in this document, using currently available LSC instruments, has a detection limit of approximately 5 Bq·kg−1 to 20 Bq·kg−1, which is lower than the WHO criteria for safe consumption of drinking water (100 Bq l−1)[3]. These values can be achieved with a counting time of 30 min for a sample volume varying between 14 ml to 40 ml. The method presented in this document is not intended for the determination of ultra-trace amount of 99Tc.
The activity concentration values in this document are expressed by sample mass unit instead of sample volume unit as it is usually the case in similar standards. The reason is that 99Tc is measured in various matrix types such as fresh water or sea water, which have significant differences in density. The activity concentration values can be easily converted to sample volume unit by measuring the sample volume. However, it increases the uncertainty on the activity concentration result.
The method described in this document is applicable in the event of an emergency situation, but not if 99mTc is present at quantities that could cause interference and not if 99mTc is used as a recovery tracer.
The analysis of Tc adsorbed to suspended matter is not covered by this method.
It is the user's responsibility to ensure the validity of this test method for the water samples tested.
|
Published |
2019-11 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 25980 |
Health and safety in welding and allied processes — Transparent welding curtains, strips and screens for arc welding processes |
|
Under development |
2023-05 |
Edition : 2 |
|
Technical Committee |
13.100
Occupational safety. Industrial hygiene
;
25.160.10
Welding processes
|
| ISO 22125-2:2019 |
Water quality — Technetium-99 — Part 2: Test method using inductively coupled plasma mass spectrometry (ICP-MS) |
This document specifies a method for the measurement of 99Tc in all types of water by inductively coupled plasma mass spectrometry (ICP-MS).
The method is applicable to test samples of supply/drinking water, rainwater, surface and ground water, as well as cooling water, industrial water, domestic, and industrial wastewater after proper sampling and handling and test sample preparation. A filtration of the test sample is necessary.
The detection limit depends on the sample volume and the instrument used. The method described in this document, using currently available ICP-MS, has a detection limit of approximately 0,2 ng·kg−1 to 0,5 ng·kg−1 (0,1 Bq·kg−1 to 0,3 Bq·kg−1), which is much lower than the WHO criteria for safe consumption of drinking water (100 Bq·l−1)[3]. The method presented in this document is not intended for the determination of ultra-trace amount of 99Tc.
The mass concentration values in this document are expressed by sample mass unit instead of sample volume unit as it is usually the case in similar standards. The reason is that 99Tc is measured in various matrix types such as fresh water or sea water, which have significant differences in density. The mass concentration values can be easily converted to sample volume unit by measuring the sample volume. However, it increases the uncertainty on the mass concentration result.
The method described in this document is applicable in the event of an emergency situation, but not if 99mTc is present at quantities that could cause interference.
The analysis of Tc adsorbed to suspended matter is not covered by this method.
It is the user's responsibility to ensure the validity of this test method for the water samples tested.
|
Published |
2019-11 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 22515:2021 |
Water quality — Iron-55 — Test method using liquid scintillation counting |
This document specifies a test method for the determination of iron-55 (55Fe) activity concentration in samples of all types of water using liquid scintillation counting (LSC). Using currently available liquid scintillation counters, this test method can measure the 55Fe activity concentrations in the range from the limit of detection up to 120 mBq l-1. These values can be achieved with a counting time between 7 200 s and 10 800 s for a sample volume from 0,5 l to 1,5 l. Higher activity concentrations can be measured by either diluting the sample or using smaller sample aliquots or both.
NOTE These performance indicators are wholly dependent on the measurement regimes in individual laboratories; in particular, the detection limits are influenced by amount of stable iron present.
The range of application depends on the amount of dissolved material in the water and on the performance characteristics of the measurement equipment (background count rate and counting efficiency).
It is the laboratory’s responsibility to ensure the suitability of this test method for the water samples tested.
|
Published |
2021-05 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| 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 23547:2022 |
Measurement of radioactivity — Gamma emitting radionuclides — Reference measurement standard specifications for the calibration of gamma-ray spectrometers |
This document specifies the characteristics of solid, liquid or gas sources of gamma emitting radionuclides used as reference measurement standards for the calibration of gamma-ray spectrometers. These reference measurement standards are traceable to national measurement standards.
This document does not describe the procedures involved in the use of these reference measurement standards for the calibration of gamma-ray spectrometers. Such procedures are specified in ISO 20042 and other documents.
This document specifies recommended reference radiations for the calibration of gamma-ray spectrometers. This document covers, but is not restricted to, gamma emitters which emit photons in the energy range of 60 keV to 1 836 keV. These reference radiations are realized in the form of point sources or adequately extended sources specified in terms of activity which are traceable to national standards.
Liquid standards that are intended to be used for preparing extended standards by the laboratories are also within the scope of this document. Reference materials (RMs) produced in accordance with ISO 17034 are out of scope of this document.
|
Published |
2022-05 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/CD 23548 |
Measurement of radioactivity — Alpha emitting radionuclides — Generic test method using alpha spectrometry |
|
Under development |
|
Edition : 1 |
|
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51275:2013 |
Practice for use of a radiochromic film dosimetry system |
ISO/ASTM 51275:2013 is a practice for using radiochromic film dosimetry systems to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water.
Radiochromic film dosimetry systems are generally used as routine dosimetry systems.
The radiochromic film dosimeter is classified as a Type II dosimeter on the basis of the complex effect of influence quantities.
ISO/ASTM 51275:2013 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ASTM E2628 for a radiochromic film dosimetry system. It is intended to be read in conjunction with ASTM E2628.
|
Published |
2013-06 |
Edition : 3 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 23655-1:2022 |
Water quality — Nickel-59 and nickel-63 — Part 1: Test method using liquid scintillation counting |
This document specifies the determination of nickel-59 and nickel-63 (59Ni and 63Ni) activity concentration in samples of all types of water using liquid scintillation counting (LSC). Using currently available liquid scintillation counters, this test method can measure 59Ni activity concentrations of 50 mBq·l−1 and 63Ni activity concentrations of 20 mBq·l−1 with a counting time of 200 min and a sample volume of 1,5 l.
NOTE These performance indicators are wholly dependent on the measurement regimes in individual laboratories; in particular, the detection limits for 59Ni are entirely dependent on the levels of 63Ni that can be present.
The range of application depends on the amount of dissolved material in the water and on the performance characteristics of the measurement equipment (background count rate and detection efficiency).
It is the laboratory’s responsibility to ensure the suitability of this test method for the water samples tested.
|
Published |
2022-09 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 23655-2:2022 |
Water quality — Nickel-59 and nickel-63 — Part 2: Test method using ICP-MS |
This document specifies the determination of nickel-59 and nickel-63 (59Ni and 63Ni) activity concentration in samples of all types of water using inductively coupled plasma mass spectrometry (ICP-MS).
Using currently available ICP-MS, this test method can measure 59Ni activity concentrations of 300 mBq⋅l−1 and 63Ni activity concentrations of 200 Bq⋅l−1. These values can be achieved with a sample volume of 1,0 l. Higher activity concentrations can be measured by either diluting the sample or using smaller sample aliquots or both.
NOTE These performance indicators are wholly dependent on the measurement regimes in individual laboratories; in particular, the detection limit is influenced by amount of stable nickel present.
The range of application depends on the amount of dissolved material in the water and on the performance characteristics of the measurement equipment (background count rate and counting efficiency).
It is the laboratory’s responsibility to ensure the suitability of this test method for the water samples tested.
|
Published |
2022-09 |
Edition : 1 |
Number of pages : 15 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| 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/ASTM 51026:2015 |
Practice for using the Fricke dosimetry system |
ISO/ASTM 51026:2015 practice covers the procedures for preparation, testing and using the acidic aqueous ferrous ammonium sulfate solution dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. The system will be referred to as the Fricke dosimetry system. The Fricke dosimetry system may be used as either a reference standard dosimetry system or a routine dosimetry system.
|
Published |
2015-07 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51204:2002 |
Practice for dosimetry in gamma irradiation facilities for food processing |
This practice outlines dosimetric procedures to be followed in irradiator characterization, process qualification, and routine processing of food with ionizing radiation from isotopic gamma sources to ensure that all the product has been treated within a predetermined range of absorbed dose. Other procedures related to irradiator characterization, process qualification, and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory dose limits for food products is not within the scope of this practice (see ASTM Guides F 1355 and F 1356).
NOTE 1 Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in the production of safe and wholesome food.
NOTE 2 ISO/ASTM Practice 51431 describes dosimetric procedures for electron beam and bremsstrahlung (X-ray) irradiation facilities for food processing.
For guidance in the selection and calibration of dosimeters, and interpretation of measured absorbed dose in the product, see ISO/ASTM Guide 51261 and ASTM Practice E 666. For the use of specific dosimetry systems, see ASTM Practices E 668, E 1026 and ISO/ASTM Practices 51205, 51275, 51276, 51310, 51401, 51538, 51540, 51607 and 51650. For discussion of radiation dosimetry for gamma rays and X-rays also see ICRU Report 14.
This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety and health practices and determine the applicability of regulatory limitations prior to use.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
|
| ISO/ASTM 51204:2004 |
Practice for dosimetry in gamma irradiation facilities for food processing |
ISO/ASTM 51204:2004 outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance qualification, and routine processing in facilities that process food with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to operational qualification, performance qualification, and routine processing that may influence absorbed dose in the product are also discussed.
Information about effective or regulatory dose limits for food products is not within the scope of ISO/ASTM 51204:2004. ISO/ASTM 51204:2004 does not provide guidance in the selection and calibration of dosimetry systems, and interpretation of measured absorbed dose in the product or the use of specific dosimetry systems.
ISO/ASTM 51204:2004 does not purport to address all of the safety concerns, if any, associated with its use.
|
Withdrawn |
2004-08 |
Edition : 2 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
|
| ISO/ASTM 51205:2002 |
Practice for use of a ceric-cerous sulfate dosimetry system |
ISO/ASTM 51205 covers the preparation, testing and procedure for using the ceric-cerous sulfate dosimetry system to measure absorbed doses in water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system is referred to as the ceric-cerous system. It is classified as a reference standard dosimetry system. Ceric-cerous dosimeters are also used as transfer standard dosimeters or routine dosimeters. ISO/ASTM 51205 describes both the spectrophotometric and the potentiometric read-out procedures for the ceric-cerous systems.
The practice described applies only to gamma rays, X rays and high energy electrons and is applicable provided the following are satisfied:
the absorbed-dose range is between 5 times 102 and 5 times 10 4 Gy;
the absorbed-dose rate is less than 106 Gy/s;
for radionuclide gamma-ray sources, the initial photon energy is greater than 0,6 MeV;
for bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons is equal to or greater than 2 MeV;
for electron beams, the initial electron energy is greater than 8 MeV.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51205:2009 |
Practice for use of a ceric-cerous sulfate dosimetry system |
ISO 51205:2009 applies to the procedures for preparation, testing, and using the ceric-cerous sulfate dosimetry system to determine absorbed dose (in terms of absorbed dose to water) in materials irradiated by photons (gamma radiation or X-radiation/bremsstrahlung) or high-energy electrons. The system consists of a dosimeter and appropriate analytical instrumentation.
The system is classified as a reference–standard dosimetry system but can also be used as a transfer–standard dosimeter or a routine dosimeter.
|
Withdrawn |
2009-06 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51205:2017 |
Practice for use of a ceric-cerous sulfate dosimetry system |
1.1 This practice covers the preparation, testing, and procedure for using the ceric-cerous sulfate dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the ceric-cerous system. The ceric-cerous dosimeter is classified as a type 1 dosimeter on the basis of the effect of influence quantities. The ceric-cerous system may be used as a reference standard dosimetry system or as a routine dosimetry system.
1.2 ISO/ASTM 51205:2017 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the ceric-cerous system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.
1.3 This practice describes both the spectrophotometric and the potentiometric readout procedures for the ceric-cerous system.
1.4 This practice applies only to gamma radiation, X-radiation/bremsstrahlung, and high energy electrons.
|
Published |
2017-05 |
Edition : 3 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51261:2002 |
Guide for selection and calibration of dosimetry systems for radiation processing |
ISO/ASTM 51261 covers the basis for selecting and calibrating dosimetry systems used to measure absorbed doses in gamma-ray or X-ray fields and in electron beams used for radiation processing. It discusses the types of dosimetry systems that may be used during calibration or on a routine basis as part of quality assurance in commercial radiation processing of products. ISO/ASTM 51261 also discusses interpretation of absorbed doses and briefly outlines measurements of the uncertainties associated with the dosimetry. The details of the calibration of the analytical instrumentation are addressed in individual dosimetry system standard practices.
The absorbed-dose range covered is up to 1 MGy (100 Mrad). Source energies covered are from 0,1 to 50 MeV photons and electrons.
This International Standard should be used along with standard practices and guides for specific dosimetry systems and applications covered in other standards. It does not cover dosimetry for radiation processing with neutrons or heavy charged particles.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51261:2013 |
Practice for calibration of routine dosimetry systems for radiation processing |
ISO/ASTM 51261:2013 specifies the requirements for calibrating routine dosimetry systems for use in radiation processing, including establishing measurement traceability and estimating uncertainty in the measured dose using the calibrated dosimetry system.
NOTE 1 — Regulations or other directives exist in many countries that govern certain radiation processing applications such as sterilization of healthcare products and radiation processing of food requiring that absorbed-dose measurements be traceable to national or international standards (ISO 11137-1, Refs (1-3)2).
|
Published |
2013-04 |
Edition : 2 |
Number of pages : 18 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51275:2002 |
Practice for use of a radiochromic film dosimetry system |
ISO/ASTM 51275 covers the handling, testing and procedure for using a radiochromic film dosimetry system to measure absorbed doses in materials irradiated by photons or electrons in terms of absorbed dose in water. This practice applies to radiochromic film dosimeters that can be used within part or all of the specified ranges as follows:
absorbed dose range 1 Gy to 100 kGy;
absorbed dose rate 1 times 10-2 Gy/s to 1 times 10 13 Gy/s;
radiation energy range for both photons and electrons 0,1 MeV to 50 MeV;
irradiation temperature range - 78 to + 60°C.
ISO/ASTM applies to radiochromic films of various formats, including small pieces used to measure a single dose value, strips used for one-dimensional dose-mapping, and sheets used for two-dimensional dose-mapping. Three-dimensional dose-mapping may be achieved by proper placement of any of these formats.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51276:2002 |
Practice for use of a polymethylmethacrylate dosimetry system |
ISO/ASTM 51276:2002 covers procedures for using hermetically sealed polymethylmethacrylate (PMMA) dosimeters for measuring absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose in water. This practice covers systems that permit absorbed dose measurements under the following conditions:
absorbed dose range is 0,1 kGy to 100 kGy;
absorbed dose rate is 1 × 10-2 to 1 × 107 Gy·s-1;
radiation energy range for photons is 0,1 MeV to 50 MeV, and for electrons 3 MeV to 50 MeV;.
irradiation temperature is - 78 °C to + 50 °C.
|
Withdrawn |
2002-12 |
Edition : 2 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51276:2012 |
Practice for use of a polymethylmethacrylate dosimetry system |
ISO/ASTM 51276:2012 provides recommendations for properly implementing dosimetry in radiation processing.
ISO/ASTM 51276:2012 specifies a practice for using polymethylmethacrylate (PMMA) dosimetry systems to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. The PMMA dosimetry system is classified as a routine dosimetry system. The PMMA dosimeter is classified as a Type II dosimeter on the basis of the complex effect of influence quantities.
ISO/ASTM 51276:2012 is applicable to the use of PMMA dosimetry systems under the following conditions:
- the absorbed dose range is 0,1 kGy to 150 kGy;
- the absorbed dose rate is 1 x 10−2 Gy·s−1 to 1 x 107 Gy·s−1;
- the photon energy range is 0,1 MeV to 25 MeV;
- the electron energy range is 3 MeV to 25 MeV.
|
Withdrawn |
2012-07 |
Edition : 3 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51276:2019 |
Practice for use of a polymethylmethacrylate dosimetry system |
1.1 This is a practice for using polymethylmethacrylate (PMMA) dosimetry systems to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. The PMMA dosimetry system is generally used as a routine dosimetry system.
1.2 The PMMA dosimeter is classified as a Type II dosim-eter on the basis of the complex effect of influence quantities (see ISO/ASTM Practice 52628).
1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 "Prac-tice for Dosimetry in Radiation Processing" for a PMMA dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.
1.4 This practice covers the use of PMMA dosimetry systems under the following conditions:
1.4.1 the absorbed dose range is 0.1 kGy to 150 kGy.
1.4.2 the absorbed dose rate is1×10−2 to1×107 Gy·s−1.
1.4.3 the photon energy range is 0.1 to 25 MeV.
1.4.4 the electron energy range is 3 to 25 MeV.
1.5 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appro-priate safety, health, and environmental practices and deter-mine the applicability of regulatory limitations prior to use.
1.6 This international standard was developed in accor-dance with internationally recognized principles on standard-ization established in the Decision on Principles for the Development of International Standards, Guides and Recom-mendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
|
Published |
2019-08 |
Edition : 4 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51310:2002 |
Practice for use of a radiochromic optical waveguide dosimetry system |
ISO/ASTM 51310 covers the handling, testing and procedure for using a radiochromic optical waveguide dosimetry system to measure absorbed doses in materials irradiated by photons in terms of absorbed dose in water. This practice applies to radiochromic optical waveguide dosimeters that can be used within part or all of the specified ranges as follows:
absorbed dose range from 1 Gy to 10 000 Gy for photons;
absorbed dose rate from 0,001 Gy/s to 1 000 Gy/s;
radiation energy range for photons from 0,1 MeV to 10 MeV;
irradiation temperature range from - 78 °C to + 60 °C.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51310:2004 |
Practice for use of a radiochromic optical waveguide dosimetry system |
ISO 51310:2004 covers the procedures for handling, testing and using a radiochromic optical waveguide dosimetry system to measure absorbed dose in materials irradiated by photons in terms of absorbed dose in water.
|
Withdrawn |
2004-06 |
Edition : 2 |
Number of pages : 5 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51310:2022 |
Practice for use of a radiochromic optical waveguide dosimetry system |
1.1 This is a practice for using a radiochromic optical waveguide dosimetry system to measure absorbed dose in materials irradiated by photons and high energy electrons in terms of absorbed dose to water. The radiochromic optical waveguide dosimetry system is generally used as a routine dosimetry system.1.2 The optical waveguide dosimeter is classified as a Type II dosimeter on the basis of the complex effect of influence quantities (see ISO/ASTM Practice 52628).1.3 This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 for an optical waveguide dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.1.4 This practice applies to radiochromic optical waveguide dosimeters that can be used within part or all of the specified ranges as follows:1.4.1 The absorbed dose range is from 1 Gy to 20 000 Gy.1.4.2 The absorbed dose rate is from 0.001 Gy/s to 1000 Gy/s.1.4.3 The radiation photon energy range is from 1 MeV to 10 MeV.1.4.4 The radiation electron energy range is from 3 MeV to 25 MeV.1.4.5 The irradiation temperature range is from –78 °C to +60 °C.1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.1.7 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
|
Published |
2022-04 |
Edition : 3 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51400:2002 |
Practice for characterization and performance of a high-dose radiation dosimetry calibration laboratory |
ISO/ASTM 15400 describes the characterization and performance criteria to be met by a high-dose radiation dosimetry calibration laboratory. By meeting these criteria, the laboratory may be accredited by a recognized accreditation organization. Adherence to these criteria will ensure high standards of performance and instill confidence that the accredited laboratory is competent to provide reliable, accurate services.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51401:2002 |
Practice for use of a dichromate dosimetry system |
ISO/ASTM 51401 covers the preparation, testing, and procedure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed doses in water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system is referred to as the dichromate system and is classified as a reference standard dosimetry system.
This International Standard describes the spectrophotometric analysis procedures for the dichromate system.
It applies only to gamma-rays, X-rays and high energy electrons provided the following conditions are satisfied:
the absorbed dose range is from 2 times 103 Gy to 5 times 10 4 Gy;
the absorbed dose rate does not exceed 600 Gy/pulse with a pulse repetition rate not exceeding 12,5 Hz, or does not exceed an equivalent dose rate of 7,5 kGy/s from continuous sources;
for radionuclide gamma-ray sources, the initial photon energy is greater than 0,6 MeV;
for bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons is equal to or greater than 2 MeV
for electron beams, the initial electron energy is greater than 8 MeV;
the irradiation temperature of the dosimeter is above 0 °C and below 80 °C.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51401:2003 |
Practice for use of a dichromate dosimetry system |
ISO/ASTM 51401:2003 covers the preparation, testing, and procedure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed dose in water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the dichromate system. It is classified as a reference standard dosimetry system.
ISO/ASTM 51401:2003 describes the spectrophotometric analysis procedures for the dichromate system.
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Withdrawn |
2003-07 |
Edition : 2 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
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| ISO/ASTM 51401:2013 |
Practice for use of a dichromate dosimetry system |
ISO/ASTM 51401:2013 covers the preparation, testing, and procedure for using the acidic aqueous silver dichromate dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the dichromate system. The dichromate dosimeter is classified as a type I dosimeter on the basis of the effect of influence quantities. The dichromate system can be used as either a reference standard dosimetry system or a routine dosimetry system.
ISO/ASTM 51401:2013 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the dichromate dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.
ISO/ASTM 51401:2013 describes the spectrophotometric analysis procedures for the dichromate system. It applies only to gamma radiation, X-radiation/bremsstrahlung, and high energy electrons.
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Published |
2013-11 |
Edition : 3 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
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| ISO/ASTM 51431:2002 |
Practice for dosimetry in electron and bremsstrahlung irradiation facilities for food processing |
ISO/ASTM 51431 describes dosimetric procedures to be followed in facility characterization, process qualification and routine processing for electron beam and bremsstrahlung irradiation facilities for food processing in order to ensure that the product receives an acceptable range of absorbed doses. Other procedures related to facility characterization, process qualification and routine product processing that may influence and be used to monitor absorbed doses in the product are also discussed.
The electron energy range covered in this practice is from 0,3 MeV to 10 MeV. Such electrons can be generated in continuous or pulse modes.
The maximum electron energy of bremsstrahlung facilities covered in this practice is 10 MeV. A photon beam can be generated by inserting a bremsstrahlung converter in the electron beam path.
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Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
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| ISO/ASTM 51431:2005 |
Practice for dosimetry in electron beam and X-ray (bremsstrahlung) irradiation facilities for food processing |
ISO/ASTM 51431:2005 outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance qualification and routine processing in facilities that process food with high-energy electrons and X-rays (bremsstrahlung) to ensure that the product has been treated within a predetermined range of absorbed dose. Other procedures related to operational qualification, performance qualification and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory dose limits for food products, and appropriate energy limits for electron beams used directly or to generate X-rays is not within the scope of this practice (see ASTM Guides F 1355, F 1356, F 1736, and F 1885).
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Withdrawn |
2005-05 |
Edition : 2 |
Number of pages : 14 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
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| ISO/ASTM 51540:2004 |
Practice for use of a radiochromic liquid dosimetry system |
ISO 51540:2004 covers the procedures for preparation of, handling, testing and using radiochromic liquid dosimetry systems of radiochromic dye solutions held in sealed or capped containers (for example, ampoules, vials). It also covers the use of spectrophotometric or photometric readout equipment for measuring absorbed dose in materials irradiated by photons and electrons.
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Withdrawn |
2004-06 |
Edition : 2 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/R 202:1961 |
Flattening test on steel tubes |
|
Withdrawn |
1961-06 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
23.040.10
Iron and steel pipes
;
77.040.10
Mechanical testing of metals
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| ISO/ASTM 51538:2002 |
Practice for use of the ethanol-chlorobenzene dosimetry system |
ISO/ASTM 51538 covers the preparation, handling, testing and procedure for using the ethanol-chlorobenzene dosimetry system to measure absorbed doses in materials irradiated by photons and electrons in terms of absorbed dose in water. The system consists of a dosimeter and appropriate analytical instrumentation. This practice describes the titration analysis as a standard readout procedure for the ECB dosimeter and applies only to gamma rays, X rays and high-energy electrons.
This practice applies provided the following are satis-fied:
the absorbed dose range is from 10 Gy to 2 MGy;
the absorbed dose rate does not exceed 106 Gy s -1;
for radionuclide gamma-ray sources, the initial photon energy is greater than 0,6 MeV;
for bremsstrahlung photons, the initial energy of the electrons used to produce the bremsstrahlung photons is equal to or greater than 2 MeV;
for electron beams, the initial electron energy is equal to or greater than 4 MeV.
the irradiation temperature of the dosimeter is within the range from - 40 °C to 80°C;
the effects of size and shape of the irradiation vessel on the response of the dosimeter can adequately be taken into account by performing the appropriate calculations using cavity theory.
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Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51538:2009 |
Practice for use of the ethanol-chlorobenzene dosimetry system |
ISO 51538:2009 covers the procedure for preparation, handling, testing, and use of the ethanol-chlorobenzene (ECB) dosimetry system to determine absorbed dose (in terms of absorbed dose to water) in materials irradiated by photons (gamma radiation or X-radiation/bremsstrahlung) or high energy electrons. The system consists of a dosimeter and appropriate analytical instrumentation. It is classified as a reference-standard dosimetry system and is also used as a routine dosimetry system.
ISO 51538:2009 describes the mercurimetric titration analysis as a standard readout procedure for the ECB dosimeter when used as a reference standard dosimetry system. Other readout methods (spectrophotometric, oscillometric) that are applicable when the ECB system is used as a routine dosimetry system are described.
ISO 51538:2009 applies provided the following conditions are satisfied.
The absorbed dose range is between 10 Gy and 2 MGy for gamma radiation and between 10 Gy and 200 kGy for high current electron accelerators.The absorbed-dose rate is less than 106 Gy s−1.For radionuclide gamma-ray sources, the initial photon energy is greater than 0,6 MeV. For bremsstrahlung photons, the energy of the electrons used to produce the bremsstrahlung photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is equal to or greater than 4 MeV. The ECB system may be used at energies of incident electrons lower than 4 MeV by employing thinner (in the beam direction) dosimeters. The ECB system may also be used at X-ray energies as low as 120 kVp. However, in this range of photon energies the effect caused by the ampoule wall is considerable.
The irradiation temperature of the dosimeter is within the range from −40°C to 80°C. The effects of size and shape of the dosimeter on the response of the dosimeter can adequately be taken into account by performing the appropriate calculations using cavity theory.
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Withdrawn |
2009-06 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51538:2017 |
Practice for use of the ethanol-chlorobenzene dosimetry system |
1.1 This practice covers the preparation, handling, testing, and procedure for using the ethanol-chlorobenzene (ECB) dosimetry system to measure absorbed dose to water when exposed to ionizing radiation. The system consists of a dosimeter and appropriate analytical instrumentation. For simplicity, the system will be referred to as the ECB system. The ECB dosimeter is classified as a type I dosimeter on the basis of the effect of influence quantities. The ECB dosimetry system may be used as a reference standard dosimetry system or as a routine dosimetry system.
1.2 ISO/ASTM 51538 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for the ECB system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.
1.3 This practice describes the mercurimetric titration analysis as a standard readout procedure for the ECB dosimeter when used as a reference standard dosimetry system. Other readout methods (spectrophotometric, oscillometric) that are applicable when the ECB system is used as a routine dosimetry system are described in Annex A1 and Annex A2.
1.4 This practice applies only to gamma radiation,
X-radiation/bremsstrahlung, and high energy electrons.
1.5 This practice applies provided the following conditions are satisfied:
1.5.1 The absorbed dose range is between 10 Gy and 2 MGy for gamma radiation and between 10 Gy and 200 kGy for high current electron accelerators (1, 2) (Warning?the boiling point of ethanol chlorobenzene solutions is approximately 80 °C. Ampoules may explode if the temperature during irradiation exceeds the boiling point. This boiling point may be exceeded if an absorbed dose greater than 200 kGy is given in a short period of time.)
1.5.2 The absorbed-dose rate is less than 106 Gy s−1(2).
1.5.3 For radionuclide gamma-ray sources, the initial pho-ton energy is greater than 0.6 MeV. For bremsstrahlung photons, the energy of the electrons used to produce the bremsstrahlung photons is equal to or greater than 2 MeV. For electron beams, the initial electron energy is greater than 8 MeV (3).
NOTE 1 The same response relative to 60Co gamma radiation was obtained in high-power bremsstrahlung irradiation produced bya5MeV electron accelerator (4).
NOTE 2 The lower energy limits are appropriate for a cylindrical dosimeter ampoule of 12-mm diameter. Corrections for dose gradients across the ampoule may be required for electron beams. The ECB system may be used at lower energies by employing thinner (in the beam direction) dosimeters (see ICRU Report 35). The ECB system may also be used at X-ray energies as low as 120 kVp (5). However, in this range of photon energies the effect caused by the ampoule wall is considerable.
NOTE 3 The effects of size and shape of the dosimeter on the response of the dosimeter can adequately be taken into account by performing the appropriate calculations using cavity theory (6).
1.5.4 The irradiation temperature of the dosimeter is within the range from −30 °C to 80 °C.
NOTE 4 The temperature dependence of dosimeter response is known only in this range (see 5.2). For use outside this range, the dosimetry system should be calibrated for the required range of irradiation tempera-tures.
1.6 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appro-priate safety and health practices and determine the applica-bility of regulatory limitations prior to use. Specific warnings are given in 1.5.1, 9.2 and 10.2.
1.7 This international standard was developed in accor-dance with internationally recognized principles on standard-ization established in the Decision on Principles for the Development of International Standards, Guides and Recom-mendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
|
Published |
2017-09 |
Edition : 3 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51539:2002 |
Guide for use of radiation-sensitive indicators |
ISO/ASTM 51539 covers the use of radiation-sensitive indicators in radiation processing. These indicators may be labels, papers, inks or packaging materials which undergo a colour change or become coloured when exposed to ionizing radiation.
The purpose of these indicators is to determine visually whether or not a product has been irradiated, rather than to measure different dose levels.
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Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51539:2005 |
Guide for use of radiation-sensitive indicators |
ISO/ASTM 51539:2005 covers procedures for using radiationsensitive indicators in radiation processing. These indicators may be labels, papers, inks or packaging materials which undergo a visual change when exposed to ionizing radiation.
|
Withdrawn |
2005-05 |
Edition : 2 |
Number of pages : 3 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51539:2013 |
Guide for use of radiation-sensitive indicators |
ISO/ASTM 51539:2013 covers procedures for using radiation-sensitive indicators in radiation processing. These indicators may be labels, papers, inks or packaging materials which undergo a visual change when exposed to ionizing radiation. The purpose for using indicators is to determine visually whether or not a product has been irradiated, rather than to measure different dose levels.
|
Published |
2013-10 |
Edition : 3 |
Number of pages : 3 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM PRF 51539 |
Guidance for use of radiation-sensitive indicators |
ISO/ASTM 51539:2013 covers procedures for using radiation-sensitive indicators in radiation processing. These indicators may be labels, papers, inks or packaging materials which undergo a visual change when exposed to ionizing radiation. The purpose for using indicators is to determine visually whether or not a product has been irradiated, rather than to measure different dose levels.
|
Under development |
2023-05 |
Edition : 4 |
Number of pages : 3 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51540:2002 |
Practice for use of a radiochromic liquid dosimetry system |
ISO/ASTM 51540 covers the preparation, handling, testing and procedure for using radiochromic liquid dosimetry systems of radiochromic dye solutions held in sealed or capped containers (e.g., ampoules, vials). It also covers the use of spectrophotometric or photometric read-out equipment for measuring absorbed doses in materials irradiated by photons and electrons.
This practice applies to radiochromic liquid dosimeter solutions that can be used within part or all of the specified ranges as follows:
the absorbed dose range is from 0,5 Gy to 40 000 Gy for photons and electrons;
the absorbed dose rate is from 10-3 Gy s -1to 1011 Gy s-1;
the radiation energy range for photons is from 0,01 MeV to 20 MeV;
the radiation energy range for electrons is from 0,01 MeV to 20 MeV;
the irradiation temperature range is from - 40 °C to + 60 °C.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51607:2002 |
Practice for use of the alanine-EPR dosimetriy system |
ISO/ASTM 51607 covers materials description, dosimeter preparation, instrumentation and procedures for using the alanine-EPR dosimetry system for measuring the absorbed dose in materials irradiated with photons and electrons. The system is based on electron paramagnetic resonance (EPR) spectroscopy of free radicals derived from the amino acid alanine. It is classified as a reference standard dosimetry system.
This International Standard covers alanine-EPR dosimetry systems for dose measurements under the following conditions:
the absorbed dose range is between 1 Gy and 105 Gy;
the absorbed dose rate is up to 102 Gy s -1 for continuous radiation fields and up to 5 times 107 Gy s-1 for pulsed radiation fields;
the radiation energy for photons and electrons is between 0,1 MeV and 28 MeV;
the irradiation temperature is between - 60 °C and + 90 °C.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51607:2004 |
Practice for use of the alanine-EPR dosimetry system |
ISO/ASTM 51607:2004 covers materials description, dosimeter preparation, instrumentation, and procedures for using the alanine-EPR dosimetry system for measuring the absorbed dose in the photon and electron irradiation processing of materials. The system is based on electron paramagnetic resonance (EPR) spectroscopy of free radicals derived from the amino acid alanine. ISO/ASTM 51607:2004 covers alanine-EPR dosimetry systems for dose measurements under the following conditions:
The absorbed dose range is between 1 and 105 Gy. The absorbed dose rate is up to 102 Gy/s for continuous radiation fields and up to 5 × 107 Gy/s for pulsed radiation fields. The radiation energy for photons and electrons is between 0,1 and 28 MeV. The irradiation temperature is between - 60 °C and + 90 °C.
ISO/ASTM 51607:2004 does not purport to address all of the safety concerns, if any, associated with its use.
|
Withdrawn |
2004-08 |
Edition : 2 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
|