| Name |
Description |
Abstract |
Status |
Publication date |
Edition |
Number of pages |
Technical committee |
ICS |
| ISO 11929-7:2005 |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 7: Fundamentals and general applications |
ISO 11929-7:2005 specifies suitable statistical values which allow an assessment of the detection capabilities in ionizing radiation measurements and of the physical effect quantified by the measurand. For this purpose, Bayesian statistical methods are used to specify characteristic limits.
ISO 11929-7:2005 deals with fundamentals and general applications.
|
Withdrawn |
2005-02 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-8:2005 |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 8: Fundamentals and application to unfolding of spectrometric measurements without the influence of sample treatment |
ISO 11929-8:2005 specifies a method for determination of suitable statistical values which allow an assessment of the detection capabilities in spectrometric nuclear radiation measurements, and of the physical effect quantified by a measurand (for example, a net area of a spectrometric line in an alpha- or gamma-spectrum) which is determined by evaluation of a multi-channel spectrum by unfolding methods, without the influence of sample treatment. For this purpose, Bayesian statistical methods are used to specify characteristic limits.
|
Withdrawn |
2005-02 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929:2010 |
Determination of the characteristic limits (decision threshold, detection limit and limits of the confidence interval) for measurements of ionizing radiation — Fundamentals and application |
ISO 11929:2010 specifies a procedure, in the field of ionizing radiation metrology, for the calculation of the "decision threshold", the "detection limit" and the "limits of the confidence interval" for a non-negative ionizing radiation measurand, when counting measurements with preselection of time or counts are carried out, and the measurand results from a gross count rate and a background count rate as well as from further quantities on the basis of a model of the evaluation. In particular, the measurand can be the net count rate as the difference of the gross count rate and the background count rate, or the net activity of a sample. It can also be influenced by calibration of the measuring system, by sample treatment and by other factors.
|
Withdrawn |
2010-03 |
Edition : 1 |
Number of pages : 60 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 12789-1:2008 |
Reference radiation fields — Simulated workplace neutron fields — Part 1: Characteristics and methods of production |
ISO 12789-2:2008 describes the characterization of simulated workplace
neutron fields produced by methods described in ISO 12789-1. It specifies the
procedures used for establishing the calibration conditions of radiation
protection devices in neutron fields produced by these facilities, with
particular emphasis on the scattered neutrons. The diversity of workplace
neutron fields is such that several special facilities have been built in order
to simulate them in the laboratory. In ISO 12789-2:2008, the neutron radiation
field specifications are classified by operational quantities. General methods
for characterizing simulated workplace neutron fields are
recommended.
|
Published |
2008-03 |
Edition : 1 |
Number of pages : 24 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 12789-2:2008 |
Reference radiation fields — Simulated workplace neutron fields — Part 2: Calibration fundamentals related to the basic quantities |
ISO 12789-2:2008 describes the characterization of simulated workplace neutron fields produced by methods described in ISO 12789-1. It specifies the procedures used for establishing the calibration conditions of radiation protection devices in neutron fields produced by these facilities, with particular emphasis on the scattered neutrons. The diversity of workplace neutron fields is such that several special facilities have been built in order to simulate them in the laboratory. In ISO 12789-2:2008, the neutron radiation field specifications are classified by operational quantities. General methods for characterizing simulated workplace neutron fields are recommended.
|
Published |
2008-03 |
Edition : 1 |
Number of pages : 15 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 12789:2000 |
Reference neutron radiations — Characteristics and methods of production of simulated workplace neutron fields |
|
Withdrawn |
2000-12 |
Edition : 1 |
Number of pages : 24 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 13160:2012 |
Water quality — Strontium 90 and strontium 89 — Test methods using liquid scintillation counting or proportional counting |
ISO 13160:2012 specifies the test methods and their associated principles for the measurement of the activity of 90Sr in equilibrium with 90Y, and 89Sr, pure beta-emitting radionuclides, in water samples. Different chemical separation methods are presented to produce strontium and yttrium sources, the activity of which is determined using a proportional counter (PC) or liquid scintillation counter (LSC). The selection of the test method depends on the origin of the contamination, the characteristics of the water to be analysed, the required accuracy of test results and the available resources of the laboratories.
These test methods are used for water monitoring following, past or present, accidental or routine, liquid or gaseous discharges. It also covers the monitoring of contamination caused by global fallout.
When fallout occurs immediately following a nuclear accident, the contribution of 89Sr to the total amount of strontium activity is not negligible. ISO 13160:2012 provides the test methods to determine the activity concentration of 90Sr in presence of 89Sr.
|
Withdrawn |
2012-07 |
Edition : 1 |
Number of pages : 38 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13160:2021 |
Water quality — Strontium 90 and strontium 89 — Test methods using liquid scintillation counting or proportional counting |
This document specifies conditions for the determination of 90Sr and 89Sr activity concentration in samples of environmental water using liquid scintillation counting (LSC) or proportional counting (PC).
The method is applicable to test samples of drinking water, rainwater, surface and ground water, marine water, as well as cooling water, industrial water, domestic, and industrial wastewater after proper sampling and handling, and test sample preparation. Filtration of the test sample and a chemical separation are required to separate and purify strontium from a test portion of the sample.
The detection limit depends on the sample volume, the instrument used, the sample count time, the background count rate, the detection efficiency and the chemical yield. The method described in this document, using currently available LSC counters, has a detection limit of approximately 10 mBq l−1 and 2 mBq l−1 for 89Sr and 90Sr, respectively, which is lower than the WHO criteria for safe consumption of drinking water (100 Bq·l−1 for 89Sr and 10 Bq·l−1 for 90Sr)[3]. These values can be achieved with a counting time of 1 000 min for a sample volume of 2 l.
The methods described in this document are applicable in the event of an emergency situation. When fallout occurs following a nuclear accident, the contribution of 89Sr to the total amount of radioactive strontium is not negligible. This document provides test methods to determine the activity concentration of 90Sr in presence of 89Sr.
The analysis of 90Sr and 89Sr adsorbed to suspended matter is not covered by this method.
It is the user’s responsibility to ensure the validity of this test method selected for the water samples tested.
|
Published |
2021-07 |
Edition : 2 |
Number of pages : 41 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 15568:1998 |
Practice for use of calorimetric dosimetry systems for electron beam dose measurements and dosimeter calibrations |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 13161:2011 |
Water quality — Measurement of polonium 210 activity concentration in water by alpha spectrometry |
ISO 13161:2011 specifies the measurement of 210Po activity concentration by alpha spectrometry in all kinds of natural waters.
The detection limit of this method depends on the volume of the sample, the counting time, the background count rate and the detection efficiency. In the case of drinking water, the analysis is usually carried out on the raw sample, without filtration or other pretreatment.
If suspended material has to be removed or analysed, filtration at 0,45 µm is recommended. The analysis of the insoluble fraction requires a mineralization step that is not covered by ISO 13161:2011. In this case, the measurement is made on the different phases obtained. The final activity is the sum of all the measured activity concentrations.
|
Withdrawn |
2011-10 |
Edition : 1 |
Number of pages : 15 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13161:2020 |
Water quality — Polonium 210 — Test method using alpha spectrometry |
This document specifies a method for the measurement of 210Po in all types of waters by alpha spectrometry.
The method is applicable to test samples of supply/drinking water, rainwater, surface and ground water, marine water, as well as cooling water, industrial water, domestic, and industrial wastewater after proper sampling and handling, and test sample preparation. Filtration of the test sample may be required.
The detection limit depends on the sample volume, the instrument used, the counting time, the background count rate, the detection efficiency and the chemical yield. The method described in this document, using currently available alpha spectrometry apparatus, has a detection limit of approximately 5 mBq l−1, which is lower than the WHO criteria for safe consumption of drinking water (100 mBq l−1). This value can be achieved with a counting time of 24 h for a sample volume of 500 ml.
The method described in this document is also applicable in an emergency situation.
The analysis of 210Po adsorbed to suspended matter in the sample is not covered by this method.
If suspended material has to be removed or analysed, filtration using a 0,45 μm filter is recommended. The analysis of the insoluble fraction requires a mineralization step that is not covered by this document [13]. In this case, the measurement is made on the different phases obtained. The final activity is the sum of all the measured activity concentrations.
It is the user's responsibility to ensure the validity of this test method for the water samples tested.
|
Published |
2020-07 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13162:2011 |
Water quality — Determination of carbon 14 activity — Liquid scintillation counting method |
ISO 13162:2011 specifies the conditions for the determination of 14C activity concentration in samples of environmental water or of 14C-containing water using liquid scintillation counting.
The method is applicable to the analysis of any organic molecule soluble in water that is well mixed with the scintillation cocktail. It does not apply to micelles or "large" particles (lipids, fulvic acid, humic acid, etc.) that are inadequately mixed with the scintillation cocktail and the water. Some beta energy is lost without any excitation of the scintillation cocktail and the results are underestimated. The method is not applicable to the analysis of organically bound 14C, whose determination requires additional chemical processing (such as chemical oxidation, combustion).
It is possible to determine 14C activity concentrations below 106 Bq l-1 without any sample dilution.
|
Withdrawn |
2011-11 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13162:2021 |
Water quality — Carbon 14 — Test method using liquid scintillation counting |
This document specifies a method for the measurement of 14C activity concentration in all types of water samples by liquid scintillation counting (LSC) either directly on the test sample or following a chemical separation.
The method is applicable to test samples of supply/drinking water, rainwater, surface and ground water, marine water, as well as cooling water, industrial water, domestic, and industrial wastewater.
The detection limit depends on the sample volume, the instrument used, the sample counting time, the background count rate, the detection efficiency and the chemical recovery. The method described in this document, using currently available liquid scintillation counters and suitable technical conditions, has a detection limit as low as 1 Bq∙l−1, which is lower than the WHO criteria for safe consumption of drinking water (100 Bq·l-1). 14C activity concentrations can be measured up to 106 Bq∙l-1 without any sample dilution.
It is the user’s responsibility to ensure the validity of this test method for the water samples tested.
|
Published |
2021-06 |
Edition : 2 |
Number of pages : 23 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13163:2013 |
Water quality — Lead-210 — Test method using liquid scintillation counting |
ISO 13163 specifies the determination of lead-210 (210Pb) activity concentration in samples of all types of water using liquid scintillation counting (LSC). For raw and drinking water, the sample should be degassed in order to minimize the ingrowth of 210Pb from radon-222 (222Rn).
Using currently available liquid scintillation counters, this test method can measure the 210Pb activity concentrations in the range of less than 20 mBq⋅l-1 to 50 mBq⋅l-1. These values can be achieved with a counting time between 180 min and 720 min for a sample volume from 0,5 l to 1,5 l.
Higher 210Pb activity concentrations can be measured by either diluting the sample or using smaller sample aliquots or both.
It is the laboratory's responsibility to ensure the suitability of this test method for the water samples tested.
|
Withdrawn |
2013-10 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 15569:1998 |
Practice for dosimetry in an electron-beam facility for radiation processing at energies between 300 keV and 25 MeV |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15570:1998 |
Practice for use of cellulose acetate dosimetry system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 13163:2021 |
Water quality — Lead-210 — Test method using liquid scintillation counting |
This document specifies a method for the measurement of 210Pb 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. Filtration of the test sample is necessary. Lead‑210 activity concentration in the environment can vary and usually ranges from 2 mBq l-1 to 300 mBq l-1 [27][28].
Using currently available liquid scintillation counters, the limit of detection of this method for 210Pb is generally of the order of 20 mBq l-1 to 50 mBq l-1, which is lower than the WHO criteria for safe consumption of drinking water (100 mBq l−1).[4][6] These values can be achieved with a counting time between 180 min and 720 min 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. The method presented in this document is not intended for the determination of an ultra-trace amount of 210Pb.
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).
The method described in this document is applicable to an emergency situation.
The analysis of Pb 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 |
2021-07 |
Edition : 2 |
Number of pages : 21 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-1:2013 |
Water quality — Radon-222 — Part 1: General principles |
ISO 13164-1:2013 gives general guidelines for sampling, packaging, and transporting of all kinds of water samples, for the measurement of the activity concentration of radon-222.
The test methods fall into two categories: a) direct measurement of the water sample without any transfer of phase (see ISO 13164‑2); b) indirect measurement involving the transfer of the radon-222 from the aqueous phase to another phase (see ISO 13164‑3).
The test methods can be applied either in the laboratory or on site.
The laboratory is responsible for ensuring the suitability of the test method for the water samples tested.
|
Published |
2013-09 |
Edition : 1 |
Number of pages : 25 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-2:2013 |
Water quality — Radon-222 — Part 2: Test method using gamma-ray spectrometry |
ISO 13164-2:2013 specifies a test method for the determination of radon-222 activity concentration in a sample of water following the measurement of its short-lived decay products by direct gamma-spectrometry of the water sample.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available gamma-ray instruments, range from a few becquerels per litre to several hundred thousand becquerels per litre for a 1 l test sample.
This test method can be used successfully with drinking water samples. The laboratory is responsible for ensuring the validity of this test method for water samples of untested matrices.
An annex gives indications on the necessary counting conditions to meet the required sensitivity for drinking water monitoring.
|
Published |
2013-09 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-3:2013 |
Water quality — Radon-222 — Part 3: Test method using emanometry |
ISO 13164-3:2013 specifies a test method for the determination of radon-222 activity concentration in a sample of water following its transfer from the aqueous phase to the air phase by degassing and its detection. It gives recommendations for rapid measurements performed within less than 1 h.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, range from 0,1 Bq l−1 to several hundred thousand becquerels per litre for a 100 ml test sample.
This test method is used successfully with drinking water samples. The laboratory is responsible for ensuring the validity of this test method for water samples of untested matrices.
This test method can be applied on field sites or in the laboratory.
Annexes A and B give indications on the necessary counting conditions to meet the required sensitivity for drinking water monitoring
|
Published |
2013-09 |
Edition : 1 |
Number of pages : 23 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-4:2015 |
Water quality — Radon-222 — Part 4: Test method using two-phase liquid scintillation counting |
ISO 13164-4:2015 describes a test method for the determination of radon-222 (222Rn) activity concentration in non-saline waters by extraction and liquid scintillation counting.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, are at least above 0,5 Bq l−1 for a 10 ml test sample and a measuring time of 1 h.
This test method can be used successfully with drinking water samples and it is the responsibility of the laboratory to ensure the validity of this test method for water samples of untested matrices.
Annex A gives indication on the necessary counting conditions to meet the required detection limits for drinking water monitoring.
|
Published |
2015-06 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 15571:1998 |
Practice for dosimetry in a gamma irradiation facility for radiation processing |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15572:1998 |
Guide for estimating uncertainties in dosimetry for radiation processing |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
|
| 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
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|
| 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
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|
| 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
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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
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13.060.60
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|
| 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
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| 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 15573:1998 |
Practice for dosimetry in an electron-beam facility for radiation processing at energies between 80 keV and 300 keV |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51400:2003 |
Practice for characterization and performance of a high-dose radiation dosimetry calibration laboratory |
ISO/ASTM 51400:2003 addresses the specific requirements for laboratories engaged in dosimetry calibrations involving ionizing radiation, namely, gamma-radiation, electron beams or X-radiation (bremsstrahlung) beams. It specifically describes the requirements for the characterization and performance criteria to be met by a high-dose radiation dosimetry calibration laboratory.
|
Withdrawn |
2003-07 |
Edition : 2 |
Number of pages : 10 |
Technical Committee |
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 15556:1998 |
Guide for selection and calibration of dosimetry systems for radiation processing |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15557:1998 |
Practice for use of a radiochromic film dosimetry system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15558:1998 |
Practice for use of a polymethylmethacrylate dosimetry system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15559:1998 |
Practice for use of a radiochromic optical waveguide dosimetry system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15560:1998 |
Practice for characterization and performance of a high-dose radiation dosimetry calibration laboratory |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15561:1998 |
Practice for use of a dichromate dosimetry system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15562:1998 |
Practice for dosimetry in electron and bremsstrahlung 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 15563:1998 |
Practice for use of the ethanol-chlorobenzene dosimetry system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15564:1998 |
Guide for use of radiation-sensitive indicators |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15565:1998 |
Practice for use of a radiochromic liquid dosimetry system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 15566:1998 |
Practice for use of the alanine-EPR dosimetriy system |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 6 |
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
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| 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 674:1988 |
Metallic materials — Hardness test — Calibration of standardized blocks to be used for Rockwell hardness testing machines (scales A - B - C - D - E - F - G - H - K) |
|
Withdrawn |
1988-12 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| 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 12807:1996 |
Safe transport of radioactive materials — Leakage testing on packages |
|
Withdrawn |
1996-10 |
Edition : 1 |
Number of pages : 76 |
Technical Committee |
13.280
Radiation protection
;
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 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.
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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
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| 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.
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Published |
2022-05 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
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| ISO/CD 23548 |
Measurement of radioactivity — Alpha emitting radionuclides — Generic test method using alpha spectrometry |
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Under development |
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Edition : 1 |
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Technical Committee |
17.240
Radiation measurements
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| 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.
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Published |
2013-06 |
Edition : 3 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
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