| Name |
Description |
Abstract |
Status |
Publication date |
Edition |
Number of pages |
Technical committee |
ICS |
| ISO 28077:2006 |
Photocarcinogenesis action spectrum (non-melanoma skin cancers) |
ISO/CIE 28077:2006 specifies the action spectrum for photocarcinogenesis of non-melanoma skin cancers.
|
Withdrawn |
2006-12 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
13.280
Radiation protection
;
17.180.20
Colours and measurement of light
|
| ISO/CIE 28077:2016 |
Photocarcinogenesis action spectrum (non-melanoma skin cancers) |
ISO/CIE 28077:2016 specifies the action spectrum for photocarcinogenesis of non-melanoma skin cancers.
|
Published |
2016-10 |
Edition : 2 |
Number of pages : 7 |
Technical Committee |
13.280
Radiation protection
;
17.180.20
Colours and measurement of light
|
| ISO/CIE DIS 28077 |
Photocarcinogenesis action spectrum (non-melanoma skin cancers) |
ISO/CIE 28077:2016 specifies the action spectrum for photocarcinogenesis of non-melanoma skin cancers.
|
Under development |
|
Edition : 3 |
Number of pages : 7 |
Technical Committee |
13.280
Radiation protection
;
17.180.20
Colours and measurement of light
|
| ISO 28218:2010 |
Radiation protection — Performance criteria for radiobioassay |
This International Standard provides criteria for quality assurance and control, and evaluation of performance of radiobioassay service laboratories.
Criteria and guidance for in vivo radiobioassay and in vitro radiobioassay are given in separate clauses.
The following are within the scope of this International Standard:
the accuracy of
in vivo measurements of activity and quantities of selected important radionuclides in test phantoms, and
in vitro measurements of activity and quantities of selected important radionuclides in test samples;
minimal requirements for detection limit;
minimum testing levels and testing ranges;
requirements for reporting radiobioassay results by service laboratories;
quality assurance in service laboratories;
quality control in service laboratories;
protocol for reporting test evaluations by service laboratories to the testing laboratory;
default procedures when the service laboratory customer does not specify the performance criteria;
applications of y# for different methods (see Annexes A and B).
The following are not within the scope of this International Standard:
detailed radiochemical methods for separating radionuclides from biological samples;
detailed procedures for in vivo and in vitro radioactivity measurements;
biokinetic data and mathematical models for converting radiobioassay results into dose (dose assessment);
procedures for the preparation and distribution of test samples and phantoms by the testing laboratories.
|
Published |
2010-10 |
Edition : 1 |
Number of pages : 45 |
Technical Committee |
13.280
Radiation protection
|
| ISO 4037-4:2019 |
Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 4: Calibration of area and personal dosemeters in low energy X reference radiation fields |
This document gives guidelines on additional aspects of the characterization of low energy photon radiations and on the procedures for calibration and determination of the response of area and personal dose(rate)meters as a function of photon energy and angle of incidence. This document concentrates on the accurate determination of conversion coefficients from air kerma to Hp(10), H*(10), Hp(3) and H'(3) and for the spectra of low energy photon radiations. As an alternative to the use of conversion coefficients the direct calibration in terms of these quantities by means of appropriate reference instruments is described.
|
Published |
2019-01 |
Edition : 2 |
Number of pages : 18 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 29661:2012 |
Reference radiation fields for radiation protection — Definitions and fundamental concepts |
ISO 29661:2012 defines terms and fundamental concepts for the calibration of dosemeters and equipment used for the radiation protection dosimetry of external radiation -- in particular, for beta, neutron and photon radiation. It defines the measurement quantities for radiation protection dosemeters and doserate meters and gives recommendations for establishing these quantities. For individual monitoring, it covers whole body and extremity dosemeters (including those for the skin and the eye lens), and for area monitoring, portable and installed dosemeters. Guidelines are given for the calibration of dosemeters and doserate meters used for individual and area monitoring in reference radiation fields. Recommendations are made for the position of the reference point and the phantom to be used for personal dosemeters.
ISO 29661:2012 also deals with the determination of the response as a function of radiation quality and angle of radiation incidence.
ISO 29661:2012 is intended to be used by calibration laboratories and manufacturers.
|
Published |
2012-09 |
Edition : 1 |
Number of pages : 35 |
Technical Committee |
13.280
Radiation protection
|
| ISO 29661:2012/Amd 1:2015 |
Reference radiation fields for radiation protection — Definitions and fundamental concepts — Amendment 1: Reference point of personal dosemeters |
|
Published |
2015-12 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
13.280
Radiation protection
|
| ISO 4037-1:1996 |
X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 1: Radiation characteristics and production methods |
Specifies the characteristics and production methods of X and gamma reference radiation for calibrating dosemeters and rate dosemeters at air kerma rates from 10 Gy/h to 10 Gy/h and for determining their response as a function of photon energy.
|
Withdrawn |
1996-12 |
Edition : 1 |
Number of pages : 42 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 4037-1:2019 |
Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 1: Radiation characteristics and production methods |
This document specifies the characteristics and production methods of X and gamma reference radiation for calibrating protection-level dosemeters and doserate meters with respect to the phantom related operational quantities of the International Commission on Radiation Units and Measurements (ICRU)[5]. The lowest air kerma rate for which this standard is applicable is 1 µGy h?1. Below this air kerma rate the (natural) background radiation needs special consideration and this is not included in this document.
For the radiation qualities specified in Clauses 4 to 6, sufficient published information is available to specify the requirements for all relevant parameters of the matched or characterized reference fields in order to achieve the targeted overall uncertainty (k = 2) of about 6 % to 10 % for the phantom related operational quantities. The X ray radiation fields described in the informative Annexes A to C are not designated as reference X-radiation fields.
NOTE The first edition of ISO 4037-1, issued in 1996, included some additional radiation qualities for which such published information is not available. These are fluorescent radiations, the gamma radiation of the radionuclide 241Am, S-Am, and the high energy photon radiations R-Ti and R-Ni, which have been removed from the main part of this document. The most widely used radiations, the fluorescent radiations and the gamma radiation of the radionuclide 241Am, S-Am, are included nearly unchanged in the informative Annexes A and B. The informative Annex C gives additional X radiation fields, which are specified by the quality index.
The methods for producing a group of reference radiations for a particular photon-energy range are described in Clauses 4 to 6, which define the characteristics of these radiations. The three groups of reference radiation are:
a) in the energy range from about 8 keV to 330 keV, continuous filtered X radiation;
b) in the energy range 600 keV to 1,3 MeV, gamma radiation emitted by radionuclides;
c) in the energy range 4 MeV to 9 MeV, photon radiation produced by accelerators.
The reference radiation field most suitable for the intended application can be selected from Table 1, which gives an overview of all reference radiation qualities specified in Clauses 4 to 6. It does not include the radiations specified in the Annexes A, B and C.
The requirements and methods given in Clauses 4 to 6 are targeted at an overall uncertainty (k = 2) of the dose(rate) value of about 6 % to 10 % for the phantom related operational quantities in the reference fields. To achieve this, two production methods are proposed:
The first one is to produce "matched reference fields", whose properties are sufficiently well-characterized so as to allow the use of the conversion coefficients recommended in ISO 4037-3. The existence of only a small difference in the spectral distribution of the "matched reference field" compared to the nominal reference field is validated by procedures, which are given and described in detail in ISO 4037‑2. For matched reference radiation fields, recommended conversion coefficients are given in ISO 4037‑3 only for specified distances between source and dosemeter, e.g., 1,0 m and 2,5 m. For other distances, the user has to decide if these conversion coefficients can be used. If both values are very similar, e.g., differ only by 2 % or less, then a linear interpolation may be used.
The second method is to produce "characterized reference fields". Either this is done by determining the conversion coefficients using spectrometry, or the required value is measured directly using secondary standard dosimeters. This method applies to any radiation quality, for any measuring quantity and, if applicable, for any phantom and angle of radiation incidence. In addition, the requirements on the parameters specifying the reference radiations depend on the definition depth in the phantom, i.e., 0,07 mm, 3 mm and 10 mm, therefore, the requirements are different for the different depths. Thus, a given radiation field can be a "matched reference field" for the depth of 0,07 mm but not for the depth of 10 mm, for which it can then be a "characterized reference field". The conversion coefficients can be determined for any distance, provided the air kerma rate is not below 1 µGy/h.
Both methods need charged particle equilibrium for the reference field. However, this is not always established in the workplace field for which the dosemeter is calibrated. This is especially true at photon energies without inherent charged particle equilibrium at the reference depth d, which depends on the actual combination of energy and reference depth d. Electrons of energies above 65 keV, 0,75 MeV and 2,1 MeV can just penetrate 0,07 mm, 3 mm and 10 mm of ICRU tissue, respectively, and the radiation qualities with photon energies above these values are considered as radiation qualities without inherent charged particle equilibrium for the quantities defined at these depths.
To determine the dose(rate) value and the associated overall uncertainty of it, a calibration of all measuring instruments used for the determination of the quantity value is needed which is traceable to national standards.
This document does not specify pulsed reference radiation fields.
|
Published |
2019-01 |
Edition : 2 |
Number of pages : 47 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 4037-2:1997 |
X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 2: Dosimetry for radiation protection over the energy ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV |
|
Withdrawn |
1997-12 |
Edition : 1 |
Number of pages : 29 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 4037-2:2019 |
Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 2: Dosimetry for radiation protection over the energy ranges from 8 keV to 1,3 MeV and 4 MeV to 9 MeV |
This document specifies the procedures for the dosimetry of X and gamma reference radiation for the calibration of radiation protection instruments over the energy range from approximately 8 keV to 1,3 MeV and from 4 MeV to 9 MeV and for air kerma rates above 1 µGy/h. The considered measuring quantities are the air kerma free-in-air, Ka, and the phantom related operational quantities of the International Commission on Radiation Units and Measurements (ICRU)[2], H*(10), Hp(10), H'(3), Hp(3), H'(0,07) and Hp(0,07), together with the respective dose rates. The methods of production are given in ISO 4037-1.
This document can also be used for the radiation qualities specified in ISO 4037-1:2019, Annexes A, B and C, but this does not mean that a calibration certificate for radiation qualities described in these annexes is in conformity with the requirements of ISO 4037.
The requirements and methods given in this document are targeted at an overall uncertainty (k = 2) of the dose(rate) of about 6 % to 10 % for the phantom related operational quantities in the reference fields. To achieve this, two production methods of the reference fields are proposed in ISO 4037-1.
The first is to produce "matched reference fields", which follow the requirements so closely that recommended conversion coefficients can be used. The existence of only a small difference in the spectral distribution of the "matched reference field" compared to the nominal reference field is validated by procedures, which are given and described in detail in this document. For matched reference radiation fields, recommended conversion coefficients are given in ISO 4037-3 only for specified distances between source and dosemeter, e.g., 1,0 m and 2,5 m. For other distances, the user has to decide if these conversion coefficients can be used.
The second method is to produce "characterized reference fields". Either this is done by determining the conversion coefficients using spectrometry, or the required value is measured directly using secondary standard dosimeters. This method applies to any radiation quality, for any measuring quantity and, if applicable, for any phantom and angle of radiation incidence. The conversion coefficients can be determined for any distance, provided the air kerma rate is not below 1 µGy/h.
Both methods require charged particle equilibrium for the reference field. However this is not always established in the workplace field for which the dosemeter shall be calibrated. This is especially true at photon energies without inherent charged particle equilibrium at the reference depth d, which depends on the actual combination of energy and reference depth d. Electrons of energies above 65 keV, 0,75 MeV and 2,1 MeV can just penetrate 0,07 mm, 3 mm and 10 mm of ICRU tissue, respectively, and the radiation qualities with photon energies above these values are considered as radiation qualities without inherent charged particle equilibrium for the quantities defined at these depths.
This document is not applicable for the dosimetry of pulsed reference fields.
|
Published |
2019-01 |
Edition : 2 |
Number of pages : 27 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 4037-3:1999 |
X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 3: Calibration of area and personal dosemeters and the measurement of their response as a function of energy and angle of incidence |
|
Withdrawn |
1999-07 |
Edition : 1 |
Number of pages : 46 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 4037-3:2019 |
Radiological protection — X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 3: Calibration of area and personal dosemeters and the measurement of their response as a function of energy and angle of incidence |
This document specifies additional procedures and data for the calibration of dosemeters and doserate meters used for individual and area monitoring in radiation protection. The general procedure for the calibration and the determination of the response of radiation protection dose(rate)meters is described in ISO 29661 and is followed as far as possible. For this purpose, the photon reference radiation fields with mean energies between 8 keV and 9 MeV, as specified in ISO 4037-1, are used. In Annex D some additional information on reference conditions, required standard test conditions and effects associated with electron ranges are given. For individual monitoring, both whole body and extremity dosemeters are covered and for area monitoring, both portable and installed dose(rate)meters are covered.
Charged particle equilibrium is needed for the reference fields although this is not always established in the workplace fields for which the dosemeter should be calibrated. This is especially true at photon energies without inherent charged particle equilibrium at the reference depth d, which depends on the actual combination of energy and reference depth d. Electrons of energies above 65 keV, 0,75 MeV and 2,1 MeV can just penetrate 0,07 mm, 3 mm and 10 mm of ICRU tissue, respectively, and the radiation qualities with photon energies above these values are considered as radiation qualities without inherent charged particle equilibrium for the quantities defined at these depths. This document also deals with the determination of the response as a function of photon energy and angle of radiation incidence. Such measurements can represent part of a type test in the course of which the effect of further influence quantities on the response is examined.
This document is only applicable for air kerma rates above 1 µGy/h.
This document does not cover the in-situ calibration of fixed installed area dosemeters.
The procedures to be followed for the different types of dosemeters are described. Recommendations are given on the phantom to be used and on the conversion coefficients to be applied. Recommended conversion coefficients are only given for matched reference radiation fields, which are specified in ISO 4037-1:2019, Clauses 4 to 6. ISO 4037‑1:2019, Annexes A and B, both informative, include fluorescent radiations, the gamma radiation of the radionuclide 241Am, S-Am, for which detailed published information is not available. ISO 4037-1:2019, Annex C, gives additional X radiation fields, which are specified by the quality index. For all these radiation qualities, conversion coefficients are given in Annexes A to C, but only as a rough estimate as the overall uncertainty of these conversion coefficients in practical reference radiation fields is not known.
NOTE The term dosemeter is used as a generic term denoting any dose or doserate meter for individual or area monitoring.
|
Published |
2019-01 |
Edition : 2 |
Number of pages : 68 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 4037-4:2004 |
X and gamma reference radiation for calibrating dosemeters and doserate meters and for determining their response as a function of photon energy — Part 4: Calibration of area and personal dosemeters in low energy X reference radiation fields |
ISO 4037-4:2004 gives guidelines on additional aspects of the characterization of low energy photon radiations. ISO 4037-4:2004 also describes procedures for calibration and determination of the response of area and personal dose(rate)meters as a function of photon energy and angle of incidence. ISO 4037-4:2004 concentrates on the accurate determination of conversion coefficients from air kerma to Hp(10) and H*(10) for the spectra of low energy photon radiations. As an alternative to the use of conversion coefficients, the direct calibration in terms of these quantities by means of appropriate reference instruments is described.
|
Withdrawn |
2004-10 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 4037:1979 |
X and gamma reference radiations for calibrating dosemeters and dose ratemeters and for determining their response as a function of photon energy |
|
Withdrawn |
1979-05 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 4037:1979/Add 1:1983 |
X and gamma reference radiations for calibrating dosemeters and dose ratemeters and for determining their response as a function of photon energy — Addendum 1: High rate series of filtered X-radiations |
|
Withdrawn |
1983-07 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 6980-1:2006 |
Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production |
ISO 6980-1:2006 specifies the requirements for reference beta radiation fields produced by radionuclide sources to be used for the calibration of personal and area dosimeters and dose-rate meters to be used for the determination of the quantities Hp(0,07) and H'(0,07), and for the determination of their response as a function of beta particle energy and angle of incidence. It gives the characteristics of radionuclides that have been used to produce reference beta radiation fields, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta particle energy and the dose equivalent rate at a depth of 0,07 mm in the International Commission on Radiation Units and Measurements (ICRU) sphere. The energy range involved lies between 66 keV) and 3,6 MeV and the dose equivalent rates are in the range from about 10-5Sv h-1 to at least 10 Sv h-1. In addition, for some sources variations of the dose equivalent rate as a function of the angle of incidence are given.
ISO 6980-1:2006 proposes two series of beta reference radiation fields from which the radiation necessary for determining the characteristics (calibration and energy and angular dependence of response) of an instrument can be selected.
Series 1 reference radiation fields are produced by radionuclide sources used with beam flattening filters designed to give uniform dose equivalent rates over a large area at a specified distance. The proposed sources of 90Sr + 90Y, 85Kr, 204Tl and 147Pm produce maximum dose equivalent rates of approximately 200 mSv h-1.
Series 2 reference radiation fields are produced without the use of beam-flattening filters, which allows large area planar sources and a range of source-to-calibration plane distances to be used. Close to the sources, only relatively small areas of uniform dose rate are produced but this series has the advantage of extending the energy and dose rate ranges beyond those of series 1. The radionuclides used are those of series 1 with the addition of the radionuclides 14C and 106Ru + 106Rh; these sources produce dose equivalent rates of up to 10 Sv h-1.
|
Withdrawn |
2006-08 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 6980-1:2022 |
Nuclear energy — Reference beta-particle radiation — Part 1: Methods of production |
This document specifies the requirements for reference beta radiation fields produced by radioactive sources to be used for the calibration of personal and area dosemeters and dose-rate meters to be used for the determination of the quantities Hp(0,07), H'(0,07;Ω), Hp(3) and H'(3;Ω), and for the determination of their response as a function of beta particle energy and angle of incidence. The basic quantity in beta dosimetry is the absorbed-dose rate in a tissue-equivalent slab phantom. This document gives the characteristics of radionuclides that have been used to produce reference beta radiation fields, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta particle energy and the dose equivalent rate at a depth of 0,07 mm in the International Commission on Radiation Units and Measurements (ICRU) sphere. The energy range involved lies between 0,22 and 3,6 MeV maximum beta energy corresponding to 0,06 MeV to 1,1 MeV mean beta energy and the dose equivalent rates are in the range from about 10 µSv·h–1 to at least 10 Sv·h–1. In addition, for some sources, variations of the dose equivalent rate as a function of the angle of incidence are given. However, as noted in ICRU Report 56[3], the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is applicable to two series of beta reference radiation fields, from which the radiation necessary for determining the characteristics (calibration and energy and angular dependence of response) of an instrument can be selected.
Series 1 reference radiation fields are produced by radioactive sources used with beam-flattening filters designed to give uniform dose equivalent rates over a large area at a specified distance. The proposed sources of 106Ru/106Rh, 90Sr/90Y, 85Kr, 204Tl and 147Pm produce maximum dose equivalent rates of approximately 200 mSv·h–1.
Series 2 reference radiation fields are produced without the use of beam-flattening filters, which allows large area planar sources and a range of source-to-calibration plane distances to be used. Close to the sources, only relatively small areas of uniform dose rate are produced, but this series has the advantage of extending the energy and dose rate ranges beyond those of series 1. The series also include radiation fields using polymethylmethacrylate (PMMA) absorbers to reduce the maximum beta particle energy. The radionuclides used are those of series 1; these sources produce dose equivalent rates of up to 10 Sv·h–1.
|
Published |
2022-10 |
Edition : 2 |
Number of pages : 21 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 6980-2:2004 |
Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field |
ISO 6980-2:2004 specifies methods for the measurement of the directional absorbed-dose rate in a tissue-equivalent slab phantom in the ISO 6980 reference beta-particle radiation fields. The energy range of the beta-particle-emitting isotopes covered by these reference radiations is 0,066 to 3,54 MeV (maximum energy). Radiation energies outside this range are beyond the scope of this standard. While measurements in a reference geometry (depth of 0,07 mm at perpendicular incidence in a tissue-equivalent slab phantom) with a reference class extrapolation chamber are dealt with in detail, the use of other measurement systems and measurements in other geometries are also described, although in less detail. The ambient dose equivalent, H*(10) as used for area monitoring of strongly penetrating radiation is not an appropriate quantity for any beta radiation, even for that penetrating a 10 mm thick layer of ICRU tissue (i.e. Emax greater than 2 MeV). If adequate protection is provided at 0,07 mm, only rarely will one be concerned with other depths, for example 3 mm.
ISO 6980-2:2004 is geared towards organizations wishing to establish reference-class dosimetry capabilities for beta particles, and serves as a guide to the performance of dosimetry with the reference class extrapolation chamber for beta-particle dosimetry in other fields. Guidance is also provided on the statement of measurement uncertainties.
|
Withdrawn |
2004-10 |
Edition : 1 |
Number of pages : 36 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 6980-2:2022 |
Nuclear energy — Reference beta-particle radiation — Part 2: Calibration fundamentals related to basic quantities characterizing the radiation field |
This document specifies methods for the measurement of the absorbed-dose rate in a tissue-equivalent slab phantom in the ISO 6980 reference beta-particle radiation fields. The energy range of the beta-particle-emitting isotopes covered by these reference radiations is 0,22 MeV to 3,6 MeV maximum beta energy corresponding to 0,06 MeV to 1,1 MeV mean beta energy. Radiation energies outside this range are beyond the scope of this document. While measurements in a reference geometry (depth of 0,07 mm or 3 mm at perpendicular incidence in a tissue‑equivalent slab phantom) with an extrapolation chamber used as primary standard are dealt with in detail, the use of other measurement systems and measurements in other geometries are also described, although in less detail. However, as noted in ICRU 56[5], the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is intended for those organizations wishing to establish primary dosimetry capabilities for beta particles and serves as a guide to the performance of dosimetry with an extrapolation chamber used as primary standard for beta‑particle dosimetry in other fields. Guidance is also provided on the statement of measurement uncertainties.
|
Published |
2022-10 |
Edition : 2 |
Number of pages : 40 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/FDIS 8529-3 |
Neutron reference radiation fields — Part 3: Calibration of area and personal dosemeters and determination of their response as a function of neutron energy and angle of incidence |
|
Under development |
|
Edition : 2 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 6980-3:2006 |
Nuclear energy — Reference beta-particle radiation — Part 3: Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence |
ISO 6980-3:2006 describes procedures for calibrating and determining the response of dosemeters and doserate meters in terms of the International Commission on Radiation Units and Measurements (ICRU) operational quantities, that is, the directional dose equivalent and the personal dose equivalent, for radiation protection purposes.
In addition to the description of calibration procedures, this part of ISO 6980-3:2006 includes recommendations for appropriate phantoms and the way to determine appropriate conversion coefficients. Guidance is provided on the statement of measurement uncertainties and the preparation of calibration records and certificates.
|
Withdrawn |
2006-10 |
Edition : 1 |
Number of pages : 23 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 6980-3:2022 |
Nuclear energy — Reference beta-particle radiation — Part 3: Calibration of area and personal dosemeters and the determination of their response as a function of beta radiation energy and angle of incidence |
This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the International Commission on Radiation Units and Measurements (ICRU) operational quantities for radiation protection purposes. However, as noted in ICRU 56[2], the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is a guide for those who calibrate protection-level dosemeters and dose-rate meters with beta-reference radiation and determine their response as a function of beta-particle energy and angle of incidence. Such measurements can represent part of a type test during the course of which the effect of other influence quantities on the response is examined. This document does not cover the in situ calibration of fixed, installed area dosemeters. The term “dosemeter” is used as a generic term denoting any dose or dose-rate meter for individual or area monitoring. In addition to the description of calibration procedures, this document includes recommendations for appropriate phantoms and the way to determine appropriate conversion coefficients. Guidance is provided on the statement of measurement uncertainties and the preparation of calibration records and certificates.
|
Published |
2022-10 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 6980:1984 |
Reference beta radiations for calibrating dosemeters and doseratemeters and for determining their response as a function of beta radiation energy |
|
Withdrawn |
1984-07 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 6980:1996 |
Reference beta radiations for calibrating dosemeters and dose-rate meters and for determining their response as a function of beta-radiation energy |
|
Withdrawn |
1996-10 |
Edition : 2 |
Number of pages : 15 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 8529-1:2001 |
Reference neutron radiations — Part 1: Characteristics and methods of production |
This part of ISO 8529 specifies the reference neutron radiations, in the energy range from thermal up to 20 MeV,
for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response
as a function of neutron energy. Reference radiations are given for neutron fluence rates of up to 1 _ 109 m?2_s?1,
corresponding, at a neutron energy of 1 MeV, to dose-equivalent rates of up to 100 mSv_h?1.
This part of ISO 8529 is concerned only with the methods of producing and characterizing the neutron reference
radiations. The procedures for applying these radiations for calibrations are described in ISO 8529-2 and
ISO 8529-3.
The reference radiations specified are the following:
_ neutrons from radionuclide sources, including neutrons from sources in a moderator;
_ neutrons produced by nuclear reactions with charged particles from accelerators;
_ neutrons from reactors.
In view of the methods of production and use of them, these reference radiations are divided, for the purposes of
this part of ISO 8529, into the following two separate sections.
_ In clause 4, radionuclide neutron sources with wide spectra are specified for the calibration of neutronmeasuring
devices. These sources should be used by laboratories engaged in the routine calibration of
neutron-measuring devices, the particular design of which has already been type tested.
_ In clause 5, accelerator-produced monoenergetic neutrons and reactor-produced neutrons with wide or quasi
monoenergetic spectra are specified for determining the response of neutron-measuring devices as a function
of neutron energy. Since these reference radiations are produced at specialized and well equipped
laboratories, only the minimum of experimental detail is given.
For the conversion of neutron fluence into the quantities recommended for radiation protection purposes,
conversion coefficients have been calculated based on the spectra presented in normative annex A and using the
fluence-to-dose-equivalent conversion coefficients as a function of neutron energy as given in ICRP Publication 74
and ICRU Report 57.
|
Withdrawn |
2001-02 |
Edition : 1 |
Number of pages : 24 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 8529-1:2001/Cor 1:2008 |
Reference neutron radiations — Part 1: Characteristics and methods of production — Technical Corrigendum 1 |
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Published |
2008-04 |
Edition : 1 |
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Technical Committee |
17.240
Radiation measurements
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| ISO 8529-1:2021 |
Neutron reference radiations fields — Part 1: Characteristics and methods of production |
This document specifies the neutron reference radiation fields, in the energy range from thermal up to 20 MeV, for calibrating neutron-measuring devices used for radiation protection purposes and for determining their response as a function of neutron energy.
This document is concerned only with the methods of producing and characterizing the neutron reference radiation fields. The procedures for applying these radiation fields for calibrations are described in References [1] and [2].
The neutron reference radiation fields specified are the following:
— neutron fields from radionuclide sources, including neutron fields from sources in a moderator;
— neutron fields produced by nuclear reactions with charged particles from accelerators;
— neutron fields from reactors.
In view of the methods of production and use of them, these neutron reference radiation fields are divided, for the purposes of this document, into the following three separate clauses:
— In Clause 4, radionuclide neutron sources with wide spectra are specified for the calibration of neutron-measuring devices. These sources should be used by laboratories engaged in the routine calibration of neutron-measuring devices, the particular design of which has already been type tested.
— In Clause 5, accelerator-produced monoenergetic neutrons and reactor-produced neutrons with wide or quasi monoenergetic spectra are specified for determining the response of neutron‑measuring devices as a function of neutron energy. Since these neutron reference radiation fields are produced at specialized and well-equipped laboratories, only the minimum of experimental detail is given.
— In Clause 6, thermal neutron fields are specified. These fields can be produced by moderated radionuclide sources, accelerators, or reactors.
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Published |
2021-11 |
Edition : 2 |
Number of pages : 30 |
Technical Committee |
17.240
Radiation measurements
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| ISO 8529-2:2000 |
Reference neutron radiations — Part 2: Calibration fundamentals of radiation protection devices related to the basic quantities characterizing the radiation field |
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Published |
2000-08 |
Edition : 1 |
Number of pages : 31 |
Technical Committee |
17.240
Radiation measurements
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| ISO 8529-3:1998 |
Reference neutron radiations — Part 3: Calibration of area and personal dosimeters and determination of response as a function of energy and angle of incidence |
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Published |
1998-11 |
Edition : 1 |
Number of pages : 17 |
Technical Committee |
17.240
Radiation measurements
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| ISO 8769-2:1996 |
Reference sources for the calibration of surface contamination monitors — Part 2: Electrons of energy less than 0,15 MeV and photons of energy less than 1,5 MeV |
Specifies the characteristics of reference sources for the calibration of surface contamination monitors that are traceable to national measurement standards. Relates to a series of sources emitting electrones of energy less than 0,15 MeV and photons of energy less than 1,5 MeV.
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Withdrawn |
1996-11 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
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| ISO 8769:1988 |
Reference sources for the calibration of surface contamination monitors — Beta-emitters (maximum beta energy greater than 0,15 MeV) and alpha-emitters |
Specifies the characteristics of reference sources and reference radiations which take the form of adequately characterized large-area sources specified in terms of activity (per unit area) and surface emission rate. Regulatory documents refer to surface contamination in terms of activity per unit area, while the response of monitoring instruments is related directly to the radiation emitted (i.e. they indicate surface emission rate). Does not describe the procedure involved in the use of these sources (see e.g. IEC Publication 325).
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Withdrawn |
1988-06 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
17.240
Radiation measurements
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| ISO 8769:2010 |
Reference sources — Calibration of surface contamination monitors — Alpha-, beta- and photon emitters |
ISO 8769:2010 specifies the characteristics of reference sources of radioactive surface contamination, traceable to national measurement standards, for the calibration of surface contamination monitors. ISO 8769:2010 relates to alpha-emitters, beta-emitters and photon emitters of maximum photon energy not greater than 1,5 MeV. It does not describe the procedures involved in the use of these reference sources for the calibration of surface contamination monitors.
ISO 8769:2010 specifies also reference radiation for the calibration of surface contamination monitors, which takes the form of adequately characterized large area sources specified, without exception, in terms of surface emission rates, the evaluation of these quantities being traceable to national standards.
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Withdrawn |
2010-09 |
Edition : 2 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
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| ISO 8769:2016 |
Reference sources — Calibration of surface contamination monitors — Alpha-, beta- and photon emitters |
ISO 8769:2016 specifies the characteristics of reference sources of radioactive surface contamination, traceable to national measurement standards, for the calibration of surface contamination monitors. This International Standard relates to alpha-emitters, beta-emitters, and photon emitters of maximum photon energy not greater than 1,5 MeV. It does not describe the procedures involved in the use of these reference sources for the calibration of surface contamination monitors. Such procedures are specified in IEC 60325[8], IEC 62363[9], and other documents.
NOTE Since some of the proposed photon sources include filters, the photon sources are to be regarded as sources of photons of a particular energy range and not as sources of a particular radionuclide. For example, a 241Am source with the recommended filtration does not emit from the surface the alpha particles or characteristic low-energy L X-ray photons associated with the decay of the nuclide. It is designed to be a source that emits photons with an average energy of approximately 60 keV.
ISO 8769:2016 also specifies preferred reference radiations for the calibration of surface contamination monitors. These reference radiations are realized in the form of adequately characterized large area sources specified, without exception, in terms of surface emission rates which are traceable to national standards.
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Withdrawn |
2016-01 |
Edition : 3 |
Number of pages : 14 |
Technical Committee |
17.240
Radiation measurements
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| ISO 8769:2020 |
Measurement of radioactivity — Alpha-, beta- and photon emitting radionuclides — Reference measurement standard specifications for the calibration of surface contamination monitors |
This document specifies the characteristics of reference measurement standards of radioactive surface contamination, traceable to national measurement standards, for the calibration of surface contamination monitors. This document relates to alpha-emitters, beta-emitters, and photon emitters of maximum photon energy not greater than 1,5 MeV.
It does not describe the procedures involved in the use of these reference measurement standards for the calibration of surface contamination monitors. Such procedures are specified in IEC 60325[6], IEC 62363[7], and other documents.
NOTE Since some of the proposed photon standards include filters, the photon standards are to be regarded as reference measurement standards of photons of a particular energy range and not as reference measurement standards of a particular radionuclide. For example, a 241Am source with the recommended filtration does not emit from the surface the alpha particles or characteristic low-energy L X-ray photons associated with the decay of the nuclide. It is designed to be a reference measurement standard that emits photons with an average energy of approximately 60 keV.
This document also specifies preferred reference radiations for the calibration of surface contamination monitors. These reference radiations are realized in the form of adequately characterized large area sources specified, without exception, in terms of surface emission rate and activity which are traceable to national standards.
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Published |
2020-06 |
Edition : 4 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
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| ISO 8963:1988 |
Dosimetry of X and gamma reference radiations for radiation protection over the energy range from 8 keV to 1,3 MeV |
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Withdrawn |
1988-11 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
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| ISO 22863-10:2021 |
Fireworks — Test methods for determination of specific chemical substances — Part 10: Nitrogen content in nitrocellulose by iron(II) sulfate titration |
This document specifies the method for determination of the nitrogen content in nitrocellulose within pyrotechnic compositions of fireworks by iron(II) sulphate titration.
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Published |
2021-02 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
71.100.30
Explosives. Pyrotechnics and fireworks
|
| ISO 9696:2007 |
Water quality — Measurement of gross alpha activity in non-saline water — Thick source method |
ISO 9696:2007 specifies a method for the determination of gross alpha activity in non-saline waters for alpha‑emitting radionuclides which are not volatile at 350 °C. It is possible to determine supported volatile radionuclides measured to an extent determined by half-life, matrix retention (of the volatile species) and the duration of measurement (counting time).
The method is applicable to raw and potable waters.
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Withdrawn |
2007-11 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
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| ISO 9696:2017 |
Water quality — Gross alpha activity — Test method using thick source |
ISO 9696:2017 specifies a method for the determination of gross alpha activity in non-saline waters for alpha-emitting radionuclides which are not volatile up to 350 °C.
The method is applicable to raw and potable waters.
The range of application depends on the amount of total soluble salts in the water and on the performance characteristics (background count rate and counting efficiency) of the counter.
It is the laboratory's responsibility to ensure the suitability of this method for the water samples tested.
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Published |
2017-10 |
Edition : 3 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
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| ISO 10647:1996 |
Procedures for calibrating and determining the response of neutron-measuring devices used for radiation protection purposes |
Specifies procedures for the calibration of neutron-measuring devices used for radiation protection purposes, and for determining their response as a function of energy, angle of incidence and dose equivalent rate, using the neutron reference radiations according to ISO 8529.
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Withdrawn |
1996-12 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
17.240
Radiation measurements
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| ISO 10703:2007 |
Water quality — Determination of the activity concentration of radionuclides — Method by high resolution gamma-ray spectrometry |
ISO 10703:2007 specifies a method for the simultaneous determination of the activity concentration of various radionuclides emitting gamma rays with energies between 40 keV and 2 MeV in water samples, by gamma‑ray spectrometry using germanium detectors with high energy resolution in combination with a multichannel analyser.
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Withdrawn |
2007-11 |
Edition : 2 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
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| ISO 10703:2021 |
Water quality — Gamma-ray emitting radionuclides — Test method using high resolution gamma-ray spectrometry |
This document specifies a method for the physical pre-treatment and conditioning of water samples and the determination of the activity concentration of various radionuclides emitting gamma-rays with energies between 40 keV and 2 MeV, by gamma‑ray spectrometry according to the generic test method described in ISO 20042.
The method is applicable to test samples of drinking water, rainwater, surface and ground water as well as cooling water, industrial water, domestic and industrial wastewater after proper sampling, sample handling, and test sample preparation (filtration when necessary and taking into account the amount of dissolved material in the water). This method is only applicable to homogeneous samples or samples which are homogeneous via timely filtration.
The lowest limit that can be measured without concentration of the sample or by using only passive shield of the detection system is about 5·10-2 Bq/l for e.g. 137Cs.1 The upper limit of the activity corresponds to a dead time of 10 %. Higher dead times may be used but evidence of the accuracy of the dead-time correction is required.
Depending on different factors, such as the energy of the gamma-rays, the emission probability per nuclear disintegration, the size and geometry of the sample and the detector, the shielding, the counting time and other experimental parameters, the sample may require to be concentrated by evaporation if activities below 5·10-2 Bq/l need to be measured. However, volatile radionuclides (e.g. radon and radioiodine) can be lost during the source preparation.
This method is suitable for application in emergency situations.
1The sample geometry: 3l Marinelli beaker; detector: GE HP N relative efficiency 55 % ; counting time: 18h.
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Published |
2021-06 |
Edition : 3 |
Number of pages : 27 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 11665-1:2012 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 1: Origins of radon and its short-lived decay products and associated measurement methods |
ISO 11665-1:2012 outlines guidance for measuring radon-222 activity concentration and the potential alpha energy concentration of its short-lived decay products in the air.
The measurement methods fall into three categories:
spot measurement methods;
continuous measurement methods;
integrated measurement methods.
ISO 11665-1:2012 provides several methods commonly used for measuring radon-222 and its short-lived decay products in air.
ISO 11665-1:2012 also provides guidance on the determination of the inherent uncertainty linked to the measurement methods described in its different parts.
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Withdrawn |
2012-07 |
Edition : 1 |
Number of pages : 30 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-1:2019 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 1: Origins of radon and its short-lived decay products and associated measurement methods |
This document outlines guidance for measuring radon-222 activity concentration and the potential alpha energy concentration of its short-lived decay products in the air.
The measurement methods fall into three categories:
a) spot measurement methods;
b) continuous measurement methods;
c) integrated measurement methods.
This document provides several methods commonly used for measuring radon-222 and its short-lived decay products in air.
This document also provides guidance on the determination of the inherent uncertainty linked to the measurement methods described in its different parts.
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Published |
2019-09 |
Edition : 2 |
Number of pages : 33 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-2:2012 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 2: Integrated measurement method for determining average potential alpha energy concentration of its short-lived decay products |
ISO 11665-2:2012 describes integrated measurement methods for short-lived radon-222 decay products. It gives indications for measuring the average potential alpha energy concentration of short-lived radon-222 decay products in the air and the conditions of use for the measuring devices.
ISO 11665-2:2012 covers samples taken over periods varying from a few weeks to one year. ISO 11665-2:2012 is not applicable to systems with a maximum sampling duration of less than one week.
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Withdrawn |
2012-07 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-2:2019 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 2: Integrated measurement method for determining average potential alpha energy concentration of its short-lived decay products |
This document describes integrated measurement methods for short-lived radon‑222 decay products[4]. It gives indications for measuring the average potential alpha energy concentration of short‑lived radon-222 decay products in the air and the conditions of use for the measuring devices.
This document covers samples taken over periods varying from a few weeks to one year. This document is not applicable to systems with a maximum sampling duration of less than one week.
The measurement method described is applicable to air samples with potential alpha energy concentration of short-lived radon-222 decay products greater than 10 nJ/m3 and lower than 1 000 nJ/m3.
NOTE For informative purposes only, this document also addresses the case of radon-220 decay products, given the similarity in behaviour of the radon isotopes 222 and 220.
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Published |
2019-09 |
Edition : 2 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-3:2012 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 3: Spot measurement method of the potential alpha energy concentration of its short-lived decay products |
ISO 11665-3:2012 describes spot measurement methods for determining the activity concentration of short-lived radon-222 decay products in the air and for calculating the potential alpha energy concentration.
ISO 11665-3:2012 gives indications for performing a spot measurement of the potential alpha energy concentration, after sampling at a given place for several minutes, and the conditions of use for the measuring devices.
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Withdrawn |
2012-07 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-3:2020 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 3: Spot measurement method of the potential alpha energy concentration of its short-lived decay products |
This document describes spot measurement methods for determining the activity concentration of short-lived radon-222 decay products in the air and for calculating the potential alpha energy concentration.
This document gives indications for performing a spot measurement of the potential alpha energy concentration, after sampling at a given place for several minutes, and the conditions of use for the measuring devices.
The measurement method described is applicable for a rapid assessment of the potential alpha energy concentration. The result obtained cannot be extrapolated to an annual estimate potential alpha energy concentration of short-lived radon-222 decay products. Thus, this type of measurement is not applicable for the assessment of annual exposure or for determining whether or not to mitigate citizen exposures to radon or radon decay products.
This measurement method is applicable to air samples with potential alpha energy concentration greater than 5 nJ/m3.
NOTE This document does not address the potential contribution of radon-220 decay products.
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Published |
2020-01 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-4:2012 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 4: Integrated measurement method for determining average activity concentration using passive sampling and delayed analysis |
ISO 11665-4:2012 describes radon-222 integrated measurement techniques with passive sampling. It gives indications for determining the average activity concentration of the radon-222 in the air from measurements based on easy-to-use and low-cost passive sampling, and the conditions of use for the sensors.
ISO 11665-4:2012 covers samples taken without interruption over periods varying from a few days to one year.
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Withdrawn |
2012-07 |
Edition : 1 |
Number of pages : 29 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-4:2020 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 4: Integrated measurement method for determining average activity concentration using passive sampling and delayed analysis |
This document describes radon-222 integrated measurement techniques with passive sampling. It gives indications for determining the average activity concentration of the radon-222 in the air from measurements based on easy-to-use and low-cost passive sampling, and the conditions of use for the sensors.
This document covers samples taken without interruption over periods varying from a few days to one year.
This measurement method is applicable to air samples with radon activity concentrations greater than 5 Bq/m3.
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Withdrawn |
2020-01 |
Edition : 2 |
Number of pages : 31 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
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| ISO 8211:1985 |
Information processing — Specification for a data descriptive file for information interchange |
|
Withdrawn |
1985-12 |
Edition : 1 |
Number of pages : 27 |
Technical Committee |
35.080
Software
|
| ISO 11665-4:2021 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 4: Integrated measurement method for determining average activity concentration using passive sampling and delayed analysis |
This document describes radon-222 integrated measurement techniques with passive sampling. It gives indications for determining the average activity concentration of the radon-222 in the air from measurements based on easy-to-use and low-cost passive sampling, and the conditions of use for the sensors.
This document covers samples taken without interruption over periods varying from a few days to one year.
This measurement method is applicable to air samples with radon activity concentrations greater than 5 Bq/m3.
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Published |
2021-03 |
Edition : 3 |
Number of pages : 31 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-5:2012 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 5: Continuous measurement method of the activity concentration |
ISO 11665-5:2012 describes continuous measurement methods for radon-222. It gives indications for continuous measuring of the temporal variations of radon activity concentration in open or confined atmospheres.
ISO 11665-5:2012 is intended for assessing temporal changes in radon activity concentration in the environment, in public buildings, in homes and in work places, as a function of influence quantities such as ventilation and/or meteorological conditions.
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Withdrawn |
2012-07 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-5:2020 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 5: Continuous measurement methods of the activity concentration |
This document describes continuous measurement methods for radon-222. It gives indications for continuous measuring of the temporal variations of radon activity concentration in open or confined atmospheres.
This document is intended for assessing temporal changes in radon activity concentration in the environment, in public buildings, in homes and in work places, as a function of influence quantities such as ventilation and/or meteorological conditions.
The measurement method described is applicable to air samples with radon activity concentration greater than 5 Bq/m3.
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Published |
2020-01 |
Edition : 2 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-6:2012 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 6: Spot measurement method of the activity concentration |
ISO 11665-6:2012 describes radon-222 spot measurement methods. It gives indications for carrying out spot measurements, at the scale of a few minutes at a given place, of the radon activity concentration in open and confined atmospheres.
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Withdrawn |
2012-07 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-6:2020 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 6: Spot measurement methods of the activity concentration |
This document describes radon-222 spot measurement methods. It gives indications for carrying out spot measurements, at the scale of a few minutes at a given place, of the radon activity concentration in open and confined atmospheres.
This measurement method is intended for rapid assessment of the radon activity concentration in the air. The result cannot be extrapolated to an annual estimate of the radon activity concentration. This type of measurement is therefore not applicable for assessment of the annual exposure or for determining whether or not to mitigate citizen exposures to radon or radon decay products.
The measurement method described is applicable to air samples with radon activity concentration greater than 50 Bq·m−3.
NOTE For example, using an appropriate device, the radon activity concentration can be spot measured in the soil and at the interface of a material with the atmosphere (see also ISO 11665-7[8]).
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Published |
2020-01 |
Edition : 2 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-7:2012 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 7: Accumulation method for estimating surface exhalation rate |
ISO 11665-7:2012 gives guidelines for estimating the radon-222 surface exhalation rate over a short period (a few hours), at a given place, at the interface of the medium (soil, rock, laid building material, walls, etc.) and the atmosphere. This estimation is based on measuring the radon activity concentration emanating from the surface under investigation and accumulated in a container of a known volume for a known duration.
This method is estimative only, as it is difficult to quantify the influence of many parameters in environmental conditions. ISO 11665-7:2012 is particularly applicable, however, in case of an investigation, a search for sources or a comparative study of exhalation rates at the same site. ISO 11665-7:2012 does not cover calibration conditions for the rate estimation devices.
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Published |
2012-07 |
Edition : 1 |
Number of pages : 23 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
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| 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.
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Withdrawn |
2003-07 |
Edition : 2 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11665-8:2012 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 8: Methodologies for initial and additional investigations in buildings |
ISO 11665-8:2012 specifies requirements for the determination of the activity concentration of radon in all types of buildings. The buildings can be single family houses, public buildings, industrial buildings, underground buildings, etc.
ISO 11665-8:2012 describes the measurement methods used to assess, during the initial investigation phase, the average annual activity concentration of radon in buildings. It also deals with investigations needed to identify the source, entry routes and transfer pathways of the radon in the building (additional investigations).
Finally, ISO 11665-8:2012 outlines the applicable requirements for the immediate post-mitigation testing of the implemented mitigation techniques, monitoring of their effectiveness and testing of the sustainability of the building's behaviour towards radon.
ISO 11665-8:2012 does not address the technical building diagnostic or the prescription of mitigation work.
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Withdrawn |
2012-11 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-8:2019 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 8: Methodologies for initial and additional investigations in buildings |
This document specifies requirements for the determination of the activity concentration of radon in all types of buildings. The buildings can be single family houses, public buildings, industrial buildings, underground buildings, etc.
This document describes the measurement methods used to assess, during the initial investigation phase, the average annual activity concentration of radon in buildings. It also deals with investigations needed to identify the source, entry routes and transfer pathways of the radon in the building (additional investigations).
Finally, this document outlines the applicable requirements for the immediate post‑mitigation testing of the implemented mitigation techniques, monitoring of their effectiveness and testing of the sustainability of the building's behaviour towards radon.
This document does not address the technical building diagnostic or the prescription of mitigation work.
|
Published |
2019-12 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-9:2016 |
Measurement of radioactivity in the environment — Air: Radon-222 — Part 9: Test methods for exhalation rate of building materials |
ISO 11665-9:2016 specifies a method for the determination of the free radon exhalation rate of a batch of mineral based building materials. The standard only refers to 222Rn exhalation determination using two test methods: Liquid Scintillation Counting (LSC) and gamma ray spectrometry (Annex A and Annex B)
The exhalation of thoron (220Rn) does not affect the test result when applying the determination methods described in this part of the standard.
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Withdrawn |
2016-02 |
Edition : 1 |
Number of pages : 38 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11665-9:2019 |
Measurement of radioactivity in the environment — Air: Radon-222 — Part 9: Test methods for exhalation rate of building materials |
This document specifies a method for the determination of the free radon exhalation rate of a batch of mineral based building materials. This document only refers to 222Rn exhalation determination using two test methods: liquid Scintillation Counting (LSC) and gamma ray spectrometry (see Annex A and Annex B).
The exhalation of thoron (220Rn) does not affect the test result when applying the determination methods described in this document.
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Published |
2019-05 |
Edition : 2 |
Number of pages : 39 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
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| ISO 11665-11:2016 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 11: Test method for soil gas with sampling at depth |
ISO 11665-11:2016 describes radon-222 test methods for soil gas using passive and active in-situ sampling at depth comprised between surface and 2 m.
ISO 11665-11:2016 gives general requirements for the sampling techniques, either passive or active and grab or continuous, for in-situ radon-222 activity concentrations measurement in soil gas.
The radon-222 activity concentration in the soil can be measured by spot or continuous measurement methods (see ISO 11665‑1). In case of spot measurement methods (ISO 11665‑6), the soil gas sampling is active only. On the other hand, the continuous methods (ISO 11665‑5) are typically associated with passive soil gas sampling.
The measurement methods are applicable to all types of soil and are determined according to the end use of the measurement results (phenomenological observation, definition or verification of mitigation techniques, etc.) taking into account the expected level of the radon-222 activity concentration.
These measurement methods are applicable to soil gas samples with radon activity concentrations greater than 100 Bq/m3.
NOTE This part of ISO 11665 is complementary with ISO 11665‑7 for characterization of the radon soil potential.
|
Published |
2016-04 |
Edition : 1 |
Number of pages : 25 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
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| ISO/TS 11665-12:2018 |
Measurement of radioactivity in the environment — Air: radon-222 — Part 12: Determination of the diffusion coefficient in waterproof materials: membrane one-side activity concentration measurement method |
This document specifies the method intended for assessing the radon diffusion coefficient in waterproofing materials such as bitumen or polymeric membranes, coatings or paints, as well as assumptions and boundary conditions which will be met during the test.
The test method described in this document allows to estimate the radon diffusion coefficient in the range of 10-5 m2/s to 10-12 m2/s[8][9] with an associated uncertainty from 10 % to 40 %.
|
Published |
2018-10 |
Edition : 1 |
Number of pages : 27 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO/TS 11665-13:2017 |
Measurement of radioactivity in the environment — Air: radon 222 — Part 13: Determination of the diffusion coefficient in waterproof materials: membrane two-side activity concentration test method |
ISO/TS 11665-13:2017 specifies the different methods intended for assessing the radon diffusion coefficient in waterproofing materials such as bitumen or polymeric membranes, coatings or paints, as well as assumptions and boundary conditions that shall be met during the test.
ISO/TS 11665-13:2017 is not applicable for porous materials, where radon diffusion depends on porosity and moisture content.
|
Published |
2017-10 |
Edition : 1 |
Number of pages : 37 |
Technical Committee |
17.240
Radiation measurements
;
13.040.01
Air quality in general
|
| ISO 11704:2010 |
Water quality — Measurement of gross alpha and beta activity concentration in non-saline water — Liquid scintillation counting method |
ISO 11704:2010 specifies a method for the determination of gross alpha and gross beta activity in waters for radionuclides which are not volatile at 80 °C. Radon isotopes and their decay products of short half life are not included in the determination.
The method is applicable to raw and potable waters with a dry residue less than 5 g/l and when no correction for colour quenching is necessary.
|
Withdrawn |
2010-07 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 11704:2018 |
Water quality — Gross alpha and gross beta activity — Test method using liquid scintillation counting |
This document specifies a method for the determination of gross alpha and gross beta activity concentration for alpha- and beta-emitting radionuclides using liquid scintillation counting (LSC).
The method is applicable to all types of waters with a dry residue of less than 5 g/l and when no correction for colour quenching is necessary.
Gross alpha and gross beta activity measurement is not intended to give an absolute determination of the activity concentration of all alpha- and beta-emitting radionuclides in a test sample, but is a screening analysis to ensure particular reference levels of specific alpha and beta emitters have not been exceeded. This type of determination is also known as gross alpha and beta index. Gross alpha and beta analysis is not expected to be as accurate nor as precise as specific radionuclide analysis after radiochemical separations.
The method covers non-volatile radionuclides below 80 °C, since some gaseous or volatile radionuclides (e.g. radon and radioiodine) can be lost during the source preparation.
The method is applicable to test samples of drinking water, rain water, surface and ground water as well as cooling water, industrial water, domestic and industrial waste water after proper sampling and test sample preparation (filtration when necessary and taking into account the amount of dissolved material in the water).
The method described in this document is applicable in the event of an emergency situation, because the results can be obtained in less than 4 h by directly measuring water test samples without any treatment.
It is the laboratory's responsibility to ensure the suitability of this test method for the water samples tested.
|
Published |
2018-11 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 11929-1:2000 |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 1: Fundamentals and application to counting measurements without the influence of sample treatment |
|
Withdrawn |
2000-07 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-1:2019 |
Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 1: Elementary applications |
The ISO 11929 series 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 coverage interval" for a non-negative ionizing radiation measurand when counting measurements with preselection of time or counts are carried out. 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.
ISO 11929 has been divided into four parts covering elementary applications in this document, advanced applications on the basis of the ISO/IEC Guide 3-1 in ISO 11929-2, applications to unfolding methods in ISO 11929-3, and guidance to the application in ISO 11929-4.
This document covers basic applications of counting measurements frequently used in the field of ionizing radiation metrology. It is restricted to applications for which the uncertainties can be evaluated on the basis of the ISO/IEC Guide 98-3 (JCGM 2008). In Annex A, the special case of repeated counting measurements with random influences is covered, while measurements with linear analogous ratemeters are covered in Annex B.
ISO 11929-2 extends the former ISO 11929:2010 to the evaluation of measurement uncertainties according to the ISO/IEC Guide 98-3-1. ISO 11929-2 also presents some explanatory notes regarding general aspects of counting measurements and on Bayesian statistics in measurements.
ISO 11929-3 deals with the evaluation of measurements using unfolding methods and counting spectrometric multi-channel measurements if evaluated by unfolding methods, in particular, for alpha- and gamma‑spectrometric measurements. Further, it provides some advice on how to deal with correlations and covariances.
ISO 11929-4 gives guidance to the application of the ISO 11929 series, summarizes shortly the general procedure and then presents a wide range of numerical examples. Information on the statistical roots of ISO 11929 and on its current development may be found elsewhere[33][34].
The ISO 11929 series also applies analogously to other measurements of any kind especially if a similar model of the evaluation is involved. Further practical examples can be found, for example, in ISO 18589[1], ISO 9696[2], ISO 9697[3], ISO 9698[4], ISO 10703[5], ISO 7503[6], ISO 28218[7], and ISO 11665[8].
NOTE A code system, named UncertRadio, is available for calculations according to ISO 11929-1 to ISO 11929-3. UncertRadio[31][32] can be downloaded for free from https://www.thuenen.de/de/fi/arbeitsbereiche/meeresumwelt/leitstelle-umweltradioaktivitaet-in-fisch/uncertradio/. The download contains a setup installation file which copies all files and folders into a folder specified by the user. After installation one has to add information to the PATH of Windows as indicated by a pop‑up window during installation. English language can be chosen and extensive "help" information is available.
|
Published |
2019-02 |
Edition : 2 |
Number of pages : 41 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-2:2000 |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 2: Fundamentals and application to counting measurements with the influence of sample treatment |
|
Withdrawn |
2000-07 |
Edition : 1 |
Number of pages : 16 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-2:2019 |
Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 2: Advanced applications |
The ISO 11929 series 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 coverage interval" for a non-negative ionizing radiation measurand when counting measurements with preselection of time or counts are carried out. 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.
ISO 11929 has been divided into four parts covering elementary applications in ISO 11929-1, advanced applications on the basis of the GUM Supplement 1 in this document, applications to unfolding methods in ISO 11929-3, and guidance to the application in ISO 11929-4.
ISO 11929-1 covers basic applications of counting measurements frequently used in the field of ionizing radiation metrology. It is restricted to applications for which the uncertainties can be evaluated on the basis of the ISO/IEC Guide 98-3 (JCGM 2008). In Annex A of ISO 11929-1:2019 the special case of repeated counting measurements with random influences is covered, while measurements with linear analogous ratemeters are covered in Annex B of ISO 11929-1:2019.
This document extends the former ISO 11929:2010 to the evaluation of measurement uncertainties according to the ISO/IEC Guide 98-3-1. It also presents some explanatory notes regarding general aspects of counting measurements and on Bayesian statistics in measurements.
ISO 11929-3 deals with the evaluation of measurements using unfolding methods and counting spectrometric multi-channel measurements if evaluated by unfolding methods, in particular, for alpha- and gamma‑spectrometric measurements. Further, it provides some advice on how to deal with correlations and covariances.
ISO 11929-4 gives guidance to the application of ISO 11929, summarizes shortly the general procedure and then presents a wide range of numerical examples. Information on the statistical roots of ISO 11929 and on its current development may be found elsewhere[30,31].
ISO 11929 also applies analogously to other measurements of any kind especially if a similar model of the evaluation is involved. Further practical examples can be found, for example, in ISO 18589[1], ISO 9696[2], ISO 9697[3], ISO 9698[4], ISO 10703[5], ISO 7503[6], ISO 28218[7], and ISO 11885[8].
NOTE A code system, named UncertRadio, is available for calculations according to ISO 119291 to ISO 11929-3. UncertRadio[27][28] can be downloaded for free from https://www.thuenen.de/en/fi/fields-of-activity/marine-environment/coordination-centre-of-radioactivity/uncertradio/. The download contains a setup installation file which copies all files and folders into a folder specified by the user. After installation one has to add information to the PATH of Windows as indicated by a pop‑up window during installation. English language can be chosen and extensive "help" information is available. . Another tool is the package ?metRology'[32] which is available for programming in R. It contains the two R functions ?uncert' and ?uncertMC' which perform the GUM conform uncertainty propagation, either analytically or by the Monte Carlo method, respectively. Covariances/correlations of input quantities are included. Applying these two functions within iterations for decision threshold and the detection limit calculations simplifies the programming effort significantly. It is also possible to implement this part of ISO 11929 in a spreadsheet containing a Monte Carlo add-in or into other commercial mathematics software.
|
Published |
2019-02 |
Edition : 2 |
Number of pages : 40 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-3:2000 |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 3: Fundamentals and application to counting measurements by high resolution gamma spectrometry, without the influence of sample treatment |
|
Withdrawn |
2000-07 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-3:2019 |
Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 3: Applications to unfolding methods |
The ISO 11929 series 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 coverage interval" for a non-negative ionizing radiation measurand when counting measurements with preselection of time or counts are carried out. 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.
ISO 11929 has been divided into four parts covering elementary applications in ISO 11929-1, advanced applications on the basis of the ISO/IEC Guide 98-3-1 in ISO 11929-2, applications to unfolding methods in this document, and guidance to the application in ISO 11929-4.
ISO 11929-1 covers basic applications of counting measurements frequently used in the field of ionizing radiation metrology. It is restricted to applications for which the uncertainties can be evaluated on the basis of the ISO/IEC Guide 98-3 (JCGM 2008). In Annex A of ISO 11929-1:2019, the special case of repeated counting measurements with random influences is covered, while measurements with linear analogous ratemeters, are covered in Annex B of ISO 11929-1:2019.
ISO 11929-2 extends the former ISO 11929:2010 to the evaluation of measurement uncertainties according to the ISO/IEC Guide 98-3-1. ISO 11929-2 also presents some explanatory notes regarding general aspects of counting measurements and on Bayesian statistics in measurements.
This document deals with the evaluation of measurements using unfolding methods and counting spectrometric multi-channel measurements if evaluated by unfolding methods, in particular, for alpha- and gamma‑spectrometric measurements. Further, it provides some advice on how to deal with correlations and covariances.
ISO 11929-4 gives guidance to the application of the ISO 11929 series, summarizes shortly the general procedure and then presents a wide range of numerical examples.
ISO 11929 Standard also applies analogously to other measurements of any kind especially if a similar model of the evaluation is involved. Further practical examples can be found, for example, in ISO 18589[7], ISO 9696[2], ISO 9697[3], ISO 9698[4], ISO 10703[5], ISO 7503[1], ISO 28218[8], and ISO 11665[6].
NOTE A code system, named UncertRadio, is available for calculations according to ISO 11929- 1 to ISO 11929-3. UncertRadio[35][36] can be downloaded for free from https://www.thuenen.de/en/fi/fields-of-activity/marine-environment/coordination-centre-of-radioactivity/uncertradio/. The download contains a setup installation file which copies all files and folders into a folder specified by the user. After installation one has to add information to the PATH of Windows as indicated by a pop‑up window during installation. English language can be chosen and extensive "help" information is available.
|
Published |
2019-02 |
Edition : 2 |
Number of pages : 39 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-4:2001 |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 4: Fundamentals and application to measurements by use of linear-scale analogue ratemeters, without the influence of sample treatment |
|
Withdrawn |
2001-06 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 1151-5:1974 |
Terms and symbols for flight dynamics — Part 5: Quantities used in measurements |
|
Withdrawn |
1974-02 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
01.060
Quantities and units
;
49.020
Aircraft and space vehicles in general
|
| ISO 11929-4:2020 |
Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 4: Guidelines to applications |
This document 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 coverage interval" for a non‑negative ionizing radiation measurand when counting measurements with preselection of time or counts are carried out. 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.
ISO 11929 has been divided into four parts covering elementary applications in ISO 11929-1, advanced applications on the basis of the ISO/IEC Guide 98-3:2008/Suppl.1 in ISO 11929-2, applications to unfolding methods in ISO 11929-3, and guidance to the application in ISO 11929-4.
ISO 11929-1 covers basic applications of counting measurements frequently used in the field of ionizing radiation metrology. It is restricted to applications for which the uncertainties can be evaluated on the basis of the ISO/IEC Guide 98-3 (JCGM 2008). In ISO 11929-1:2019, Annex A the special case of repeated counting measurements with random influences and in ISO 11929-1:2019, Annex B, measurements with linear analogous ratemeters are covered.
ISO 11929-2 extends ISO 11929-1 to the evaluation of measurement uncertainties according to the ISO/IEC Guide 98-3:2008/Suppl.1. ISO 11929-2 also presents some explanatory notes regarding general aspects of counting measurements and Bayesian statistics in measurements.
ISO 11929-3 deals with the evaluation of measurements using unfolding methods and counting spectrometric multi-channel measurements if evaluated by unfolding methods, in particular, alpha- and gamma-spectrometric measurements. Further, it provides some advice how to deal with correlations and covariances.
ISO 11929-4 gives guidance to the application of ISO 11929 (all parts), summarizing shortly the general procedure and then presenting a wide range of numerical examples. The examples cover elementary applications according to ISO 11929-1 and ISO 11929-2.
The ISO 11929 (all parts) also applies analogously to other measurements of any kind if a similar model of the evaluation is involved. Further practical examples can be found in other International Standards, for example, see References [1 to 20].
|
Withdrawn |
2020-09 |
Edition : 2 |
Number of pages : 97 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-4:2022 |
Determination of the characteristic limits (decision threshold, detection limit and limits of the coverage interval) for measurements of ionizing radiation — Fundamentals and application — Part 4: Guidelines to applications |
This document 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 coverage interval” for a non‑negative ionizing radiation measurand when counting measurements with preselection of time or counts are carried out. 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.
ISO 11929 has been divided into four parts covering elementary applications in ISO 11929-1, advanced applications on the basis of the ISO/IEC Guide 98-3:2008/Suppl.1 in ISO 11929-2, applications to unfolding methods in ISO 11929-3, and guidance to the application in ISO 11929-4.
ISO 11929-1 covers basic applications of counting measurements frequently used in the field of ionizing radiation metrology. It is restricted to applications for which the uncertainties can be evaluated on the basis of the ISO/IEC Guide 98-3 (JCGM 2008). In ISO 11929-1:2019, Annex A the special case of repeated counting measurements with random influences and in ISO 11929-1:2019, Annex B, measurements with linear analogous ratemeters are covered.
ISO 11929-2 extends ISO 11929-1 to the evaluation of measurement uncertainties according to the ISO/IEC Guide 98-3:2008/Suppl.1. ISO 11929-2 also presents some explanatory notes regarding general aspects of counting measurements and Bayesian statistics in measurements.
ISO 11929-3 deals with the evaluation of measurements using unfolding methods and counting spectrometric multi-channel measurements if evaluated by unfolding methods, in particular, alpha- and gamma-spectrometric measurements. Further, it provides some advice how to deal with correlations and covariances.
ISO 11929-4 gives guidance to the application of ISO 11929 (all parts), summarizing shortly the general procedure and then presenting a wide range of numerical examples. The examples cover elementary applications according to ISO 11929-1 and ISO 11929-2.
The ISO 11929 (all parts) also applies analogously to other measurements of any kind if a similar model of the evaluation is involved. Further practical examples can be found in other International Standards, for example, see References [1 to 20].
NOTE A code system, named UncertRadio, is available allowing for calculations according to ISO 11929-1 to ISO 11929-3. UncertRadio[40][41] can be downloaded for free from https://www.thuenen.de/en/fi/fields-of-activity/marine-environment/coordination-centre-of-radioactivity/uncertradio/. The download contains a setup installation file that copies all files and folders into a folder specified by the user. After installation one has to add information to the PATH of Windows as indicated by a pop‑up window during installation. English language can be chosen and extensive “help” information is available. Another tool is the package ‘metRology’[44] which is available for programming in R. It contains the two R functions ‘uncert’ and ‘uncertMC’ which perform the GUM-conform uncertainty propagation, either analytically or by the Monte Carlo method, respectively. Covariances/correlations of input quantities are included. Applying these two functions within iterations for decision threshold and the detection limit calculations simplifies the programming effort significantly. It is also possible to implement this document in a spreadsheet containing a Monte Carlo add-in or into other commercial mathematics software.
|
Published |
2022-07 |
Edition : 3 |
Number of pages : 95 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-5:2005 |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 5: Fundamentals and applications to counting measurements on filters during accumulation of radioactive material |
ISO 11929-5:2004 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 11929-5:2004 deals with fundamentals and applications to counting measurements on filters during accumulation of radioactive material.
|
Withdrawn |
2005-02 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 11929-6:2005 |
Determination of the detection limit and decision threshold for ionizing radiation measurements — Part 6: Fundamentals and applications to measurements by use of transient mode |
ISO 11929-6:2005 specifies suitable statistical values which allow an assessment of the detection capabilities in ionizing radiation measurements by use of a transient mode. For this purpose, statistical methods are used to specify two statistical values characterizing given probabilities of error.
ISO 11929-6:2005 deals with fundamentals and applications to measurements by use of transient mode.
|
Withdrawn |
2005-02 |
Edition : 1 |
Number of pages : 16 |
Technical Committee |
17.240
Radiation measurements
|
| 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 13591:1997 |
Small craft — Portable fuel systems for outboard motors |
|
Published |
1997-12 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
47.080
Small craft
|
| 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 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 15011-4:2006/Amd 1:2008 |
Health and safety in welding and allied processes — Laboratory method for sampling fume and gases — Part 4: Fume data sheets — Amendment 1 |
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Withdrawn |
2008-12 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
13.100
Occupational safety. Industrial hygiene
;
25.160.10
Welding processes
|
| 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.
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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.
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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.
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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 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 4226:1980 |
Air quality — General aspects — Units of measurement |
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Withdrawn |
1980-02 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
01.060
Quantities and units
;
13.040.01
Air quality in general
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| 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.
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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.
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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.
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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
|