17.240 - Radiation measurements
ICS 17.240 Details
Radiation measurements
Strahlungsmessungen
Mesurage des rayonnements
Merjenje sevanja
General Information
e-Library Subscription
Create subscription and get permanent access to documents within 17.240 - Radiation measurements
Currently subscription includes documents marked with .We are working on making all documents available within the subscription.
This document specifies the identification of radionuclides and the measurement of their activity in soil using in situ gamma spectrometry with portable systems equipped with germanium or scintillation detectors. This document is suitable to rapidly assess the activity of artificial and natural radionuclides deposited on or present in soil layers of large areas of a site under investigation. This document can be used in connection with radionuclide measurements of soil samples in the laboratory (see ISO 18589-3) in the following cases: — routine surveillance of the impact of radioactivity released from nuclear installations or of the evolution of radioactivity in the region; — investigations of accident and incident situations; — planning and surveillance of remedial action; — decommissioning of installations or the clearance of materials. It can also be used for the identification of airborne artificial radionuclides, when assessing the exposure levels inside buildings or during waste disposal operations. Following a nuclear accident, in situ gamma spectrometry is a powerful method for rapid evaluation of the gamma activity deposited onto the soil surface as well as the surficial contamination of flat objects. NOTE The method described in this document is not suitable when the spatial distribution of the radionuclides in the environment is not precisely known (influence quantities, unknown distribution in soil) or in situations with very high photon flux. However, the use of small volume detectors with suitable electronics allows measurements to be performed under high photon flux.
- Standard54 pagesEnglish languagesale 15% off
- Standard55 pagesFrench languagesale 15% off
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 98-3:2008/Suppl 1:2008 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 ISO 11929-1:2025, Annex A, the special case of repeated counting measurements with random influences is covered, while measurements with linear analogous ratemeters, are covered in ISO 11929-1:2025, Annex B. 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[ REF Reference_ref_14 \r \h 7 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310034000000 ], ISO 9696[ REF Reference_ref_9 \r \h 2 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000100000005200650066006500720065006E00630065005F007200650066005F0039000000 ], ISO 9697[ REF Reference_ref_10 \r \h 3 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310030000000 ], ISO 9698[ REF Reference_ref_11 \r \h 4 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310031000000 ], ISO 10703[ REF Reference_ref_12 \r \h 5 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310032000000 ], ISO 7503[ REF Reference_ref_8 \r \h 1 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000100000005200650066006500720065006E00630065005F007200650066005F0038000000 ], ISO 28218[ REF Reference_ref_15 \r \h 8 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310035000000 ], and ISO 11665[ REF Reference_ref_13 \r \h 6 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310033000000 ]. NOTE A code system, named UncertRadio, is available for calculations according to ISO 11929- 1 to ISO 11929-3. UncertRadio[ REF Reference_ref_42 \r \h 35 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00340032000000 ][ REF Reference_ref_43 \r \h 36 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00340033000000 ] can be downloaded
- Standard37 pagesEnglish languagesale 15% off
- Standard40 pagesFrench languagesale 15% off
This document specifies approaches for the determination of plutonium isotopes (238Pu, 239Pu and 240Pu) in urine using alpha spectrometry or inductively coupled plasma mass spectrometry (ICP-MS). It is applicable to the measurement of plutonium isotopes at levels which are appropriate for — workers handling plutonium in planned exposure situations, where detection limits are sufficiently low to be in accordance with dose limits, and — workers, members of the public and emergency responders in emergency exposure situations, where required detection limits can be much higher, and results need to be reported in a short timescale. This document does not provide information on when monitoring is carried out or the interpretation of the results in terms of dose or biological effects.
- Standard37 pagesEnglish languagesale 15% off
- Standard39 pagesFrench languagesale 15% off
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 REF Annex_sec_A \r \h Annex A 08D0C9EA79F9BACE118C8200AA004BA90B02000000080000000C00000041006E006E00650078005F007300650063005F0041000000 , the special case of repeated counting measurements with random influences is covered, while measurements with linear analogous ratemeters are covered in REF Annex_sec_B \r \h Annex B 08D0C9EA79F9BACE118C8200AA004BA90B02000000080000000C00000041006E006E00650078005F007300650063005F0042000000 . ISO 11929-2 extends the former ISO 11929:2010 to the evaluation of measurement uncertainties according to the ISO/IEC Guide 98-3:2008/Suppl 1:2008. 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[ REF Reference_ref_40 \r \h 33 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00340030000000 ][ REF Reference_ref_41 \r \h 34 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00340031000000 ]. 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[ REF Reference_ref_8 \r \h 1 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000100000005200650066006500720065006E00630065005F007200650066005F0038000000 ], ISO 9696[ REF Reference_ref_9 \r \h 2 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000100000005200650066006500720065006E00630065005F007200650066005F0039000000 ], ISO 9697[ REF Reference_ref_10 \r \h 3 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310030000000 ], ISO 9698[ REF Reference_ref_11 \r \h 4 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310031000000 ], ISO 10703[ REF Reference_ref_12 \r \h 5 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310032000000 ], ISO 7503[ REF Reference_ref_13 \r \h 6 08D0C9EA79
- Standard45 pagesEnglish languagesale 15% off
- Standard45 pagesFrench languagesale 15% off
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 ISO 11929-1:2025, Annex A, the special case of repeated counting measurements with random influences is covered, while measurements with linear analogous ratemeters are covered in ISO 11929-1:2025, Annex B. 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[ REF Reference_ref_37 \r \h 30 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00330037000000 ][ REF Reference_ref_38 \r \h 31 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00330038000000 ]. 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[ REF Reference_ref_8 \r \h 1 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000100000005200650066006500720065006E00630065005F007200650066005F0038000000 ], ISO 9696[ REF Reference_ref_9 \r \h 2 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000100000005200650066006500720065006E00630065005F007200650066005F0039000000 ], ISO 9697[ REF Reference_ref_10 \r \h 3 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310030000000 ], ISO 9698[ REF Reference_ref_11 \r \h 4 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310031000000 ], ISO 10703[ REF Reference_ref_12 \r \h 5 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310032000000 ], ISO 7503[ REF Reference_ref_13 \r \h 6 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310033000000 ], ISO 28218[ REF Reference_ref_14 \r \h 7 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310034000000 ] and ISO 11665[ REF Reference_ref_15 \r \h 8 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310035000000 ]. NOTE A code system, named UncertRadio, is available for calculations according t
- Standard40 pagesEnglish languagesale 15% off
- Standard41 pagesFrench languagesale 15% off
IEC 61874:2025 applies to equipment consisting of:
- a borehole logging probe equipped with a collimated radioisotope (gamma) source (during the actual measurements only) and a detector unit to measure scattered gamma radiation;
- a hoisting system and depth measuring system;
- other instruments and devices (power supply, pulse converter/amplifier, ratemeter, recorder, signal processing and readout units).
This document defines the terminology, specifies the types of apparatus, design and general technical requirements, specific radiation performance, electrical, mechanical, safe and environmental performance requirements. It also defines test and calibration procedures and covers electrical safety and radiation protection issues. Further, it gives recommendations about items included in the manufacturer's operation and maintenance documentation (or certificate).
The purpose of this document is to specify design requirements and performance characteristics of nuclear instrumentation used in boreholes to determine bulk rock density in situ. With suitable response charts the measurements can be equated to rock lithology and porosity.
- Standard14 pagesEnglish languagesale 15% off
This part of CISPR 16 specifies the characteristics and performance of equipment for the measurement of radiated disturbances in the frequency range 9 kHz to 18 GHz. Specifications for antennas and test sites are included.
NOTE In accordance with IEC Guide 107 [1], 1 CISPR 16-1-4 is a basic EMC publication for use by product committees of the IEC. As stated in Guide 107, product committees are responsible for determining the applicability of the EMC standard. CISPR and its sub-committees are prepared to cooperate with product committees in the evaluation of the value of particular EMC tests for specific products.
The requirements of this publication apply at all frequencies and for all levels of radiated disturbances within the CISPR indicating range of the measuring equipment.
Methods of measurement are covered in CISPR 16-2-3, further information on radio disturbance is given in CISPR TR 16-3 [2], and uncertainties, statistics, and limit modelling are covered in CISPR 16-4 series.
- Standard172 pagesEnglish languagesale 10% offe-Library read for1 day
This document 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. This document is not applicable for porous materials, where radon diffusion depends on porosity and moisture content.
- Technical specification35 pagesEnglish languagesale 15% off
ISO/IEC 11801-1:2017(E) This document specifies a multi-vendor cabling system which may be implemented with material from single or multiple sources. This part of ISO/IEC 11801 defines requirements that are common to the other parts of the ISO/IEC 11801 series. Cabling specified by this document supports a wide range of services including voice, data, and vido that may also incorporate the supply of power.
The contents of the corrigendum of April 2018 have been included in this copy.
- Standard149 pagesEnglish languagesale 15% off
- Standard425 pagesEnglish languagesale 15% off
- Amendment5 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies a screening test method to quantify rapidly the activity concentration of gamma-emitting radionuclides, such as 131I, 132Te, 134Cs and 137Cs, in solid or liquid test samples using gamma-ray spectrometry with lower resolution scintillation detectors as compared with the HPGe detectors (see IEC 61563[7]).
This test method can be used for the measurement of any potentially contaminated environmental matrices (including soil), food and feed samples as well as industrial materials or products that have been properly conditioned[8]. Sample preparation techniques used in the screening method are not specified in this document, since special sample preparation techniques other than simple machining (cutting, grinding, etc.) should not be required. Although the sampling procedure is of utmost importance in the case of the measurement of radioactivity in samples, it is out of scope of this document; other International Standards for sampling procedures that can be used in combination with this document are available (see References [9] [10] [11] [12] [13] [14]).
The test method applies to the measurement of gamma-emitting radionuclides such as 131I, 134Cs and 137Cs. Using sample sizes of 0,5 l to 1,0 l in a Marinelli beaker and a counting time of 5 min to 20 min, decision threshold of 10 Bq·kg−1 can be achievable using a commercially available scintillation spectrometer [e.g. thallium activated sodium iodide (NaI(Tl)) spectrometer 2” ϕ × 2” (50,8 mm Ø x 50,8 mm) detector size, 7 % resolution (FWHM) at 662 keV, 30 mm lead shield thickness].
This test method also can be performed in a “makeshift” laboratory or even outside a testing laboratory on samples directly measured in the field where they were collected.
During a nuclear or radiological emergency, this test method enables a rapid measurement of the activity concentration of potentially contaminated samples to check against operational intervention levels (OILs) set up by decision makers that would trigger a predetermined emergency response to reduce existing radiation risks[2].
Due to the uncertainty associated with the results obtained with this test method, test samples requiring more accurate test results can be measured using high purity germanium (HPGe) detectors gamma-ray spectrometry in a testing laboratory, following appropriate preparation of the test samples[15][16].
This document does not contain criteria to establish the activity concentration of OILs.
- Standard31 pagesEnglish languagesale 10% offe-Library read for1 day
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 0,07 MeV to 1,2 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, 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.
- Standard50 pagesEnglish languagesale 10% offe-Library read for1 day
- Amendment5 pagesEnglish languagesale 10% offe-Library read for1 day
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 MeV and 3,6 MeV maximum beta energy corresponding to 0,07 MeV to 1,2 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 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 applicable to two series of reference beta 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.
- Standard29 pagesEnglish languagesale 10% offe-Library read for1 day
This document describes a generic test method for measuring alpha emitting radionuclides, for all types of samples (soil, sediment, construction material, foodstuff, water, airborne, environmental bio-indicator, human biological samples as urine, faeces etc.) by alpha spectrometry. This method can be used for any type of environmental study or monitoring of alpha emitting radionuclides activities.
If relevant, this test method requires appropriate sample pre-treatment followed by specific chemical separation of the test portion in order to obtain a thin source proper to alpha spectrometry measurement.
This test method can be used to determine the activity, specific activity or activity concentration of a sample containing alpha emitting radionuclides such as 210Po, 226Ra, 228Th, 229Th, 230Th, 232Th, 232U,234U, 235U, 238U, 238Pu, 239+240Pu, 241Am or 243+244Cm.
This test method can be used to measure very low levels of activity, one or two orders of magnitude less than the usual natural levels of alpha emitting radionuclides. Annexes B of UNSCEAR 2000 and UNSCEAR 2008 give, respectively, typical natural activity concentrations for air, foods, drinking waters and, soils and building materials. The detection limit of the test method depends on the amount of the sample material analysed (mass or volume) after concentration, chemical yield, thickness of measurement source and counting time.
The quantity of the sample to be collected and analysed depends on the expected activity of the sample and the detection limit to achieve.
- Standard47 pagesEnglish languagesale 10% offe-Library read for1 day
This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the operational quantities for radiation protection purposes defined by the International Commission on Radiation Units and Measurements (ICRU). However, as noted in ICRU 56, 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.
- Standard27 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies a screening test method to quantify rapidly the activity concentration of gamma-emitting radionuclides, such as 131I, 132Te, 134Cs and 137Cs, in solid or liquid test samples using gamma-ray spectrometry with lower resolution scintillation detectors as compared with the HPGe detectors (see IEC 61563[7]).
This test method can be used for the measurement of any potentially contaminated environmental matrices (including soil), food and feed samples as well as industrial materials or products that have been properly conditioned[8]. Sample preparation techniques used in the screening method are not specified in this document, since special sample preparation techniques other than simple machining (cutting, grinding, etc.) should not be required. Although the sampling procedure is of utmost importance in the case of the measurement of radioactivity in samples, it is out of scope of this document; other International Standards for sampling procedures that can be used in combination with this document are available (see References [9] [10] [11] [12] [13] [14]).
The test method applies to the measurement of gamma-emitting radionuclides such as 131I, 134Cs and 137Cs. Using sample sizes of 0,5 l to 1,0 l in a Marinelli beaker and a counting time of 5 min to 20 min, decision threshold of 10 Bq·kg−1 can be achievable using a commercially available scintillation spectrometer [e.g. thallium activated sodium iodide (NaI(Tl)) spectrometer 2” ϕ × 2” (50,8 mm Ø x 50,8 mm) detector size, 7 % resolution (FWHM) at 662 keV, 30 mm lead shield thickness].
This test method also can be performed in a “makeshift” laboratory or even outside a testing laboratory on samples directly measured in the field where they were collected.
During a nuclear or radiological emergency, this test method enables a rapid measurement of the activity concentration of potentially contaminated samples to check against operational intervention levels (OILs) set up by decision makers that would trigger a predetermined emergency response to reduce existing radiation risks[2].
Due to the uncertainty associated with the results obtained with this test method, test samples requiring more accurate test results can be measured using high purity germanium (HPGe) detectors gamma-ray spectrometry in a testing laboratory, following appropriate preparation of the test samples[15][16].
This document does not contain criteria to establish the activity concentration of OILs.
- Standard31 pagesEnglish languagesale 10% offe-Library read for1 day
This document describes a generic test method for measuring alpha emitting radionuclides, for all types of samples (soil, sediment, construction material, foodstuff, water, airborne, environmental bio-indicator, human biological samples as urine, faeces etc.) by alpha spectrometry. This method can be used for any type of environmental study or monitoring of alpha emitting radionuclides activities.
If relevant, this test method requires appropriate sample pre-treatment followed by specific chemical separation of the test portion in order to obtain a thin source proper to alpha spectrometry measurement.
This test method can be used to determine the activity, specific activity or activity concentration of a sample containing alpha emitting radionuclides such as 210Po, 226Ra, 228Th, 229Th, 230Th, 232Th, 232U,234U, 235U, 238U, 238Pu, 239+240Pu, 241Am or 243+244Cm.
This test method can be used to measure very low levels of activity, one or two orders of magnitude less than the usual natural levels of alpha emitting radionuclides. Annexes B of UNSCEAR 2000 and UNSCEAR 2008 give, respectively, typical natural activity concentrations for air, foods, drinking waters and, soils and building materials. The detection limit of the test method depends on the amount of the sample material analysed (mass or volume) after concentration, chemical yield, thickness of measurement source and counting time.
The quantity of the sample to be collected and analysed depends on the expected activity of the sample and the detection limit to achieve.
- Standard47 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies a screening test method to quantify rapidly the activity concentration of gamma-emitting radionuclides, such as 131I, 132Te, 134Cs and 137Cs, in solid or liquid test samples using gamma-ray spectrometry with lower resolution scintillation detectors as compared with the HPGe detectors (see IEC 61563[7]). This test method can be used for the measurement of any potentially contaminated environmental matrices (including soil), food and feed samples as well as industrial materials or products that have been properly conditioned[8]. Sample preparation techniques used in the screening method are not specified in this document, since special sample preparation techniques other than simple machining (cutting, grinding, etc.) should not be required. Although the sampling procedure is of utmost importance in the case of the measurement of radioactivity in samples, it is out of scope of this document; other International Standards for sampling procedures that can be used in combination with this document are available (see References [ REF Reference_ref_12 \r \h 9 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310032000000 ] [10] [11] [12] [13] [14]). The test method applies to the measurement of gamma-emitting radionuclides such as 131I, 134Cs and 137Cs. Using sample sizes of 0,5 l to 1,0 l in a Marinelli beaker and a counting time of 5 min to 20 min, decision threshold of 10 Bq·kg−1 can be achievable using a commercially available scintillation spectrometer [e.g. thallium activated sodium iodide (NaI(Tl)) spectrometer 2” ϕ × 2” (50,8 mm Ø x 50,8 mm) detector size, 7 % resolution (FWHM) at 662 keV, 30 mm lead shield thickness]. This test method also can be performed in a “makeshift” laboratory or even outside a testing laboratory on samples directly measured in the field where they were collected. During a nuclear or radiological emergency, this test method enables a rapid measurement of the activity concentration of potentially contaminated samples to check against operational intervention levels (OILs) set up by decision makers that would trigger a predetermined emergency response to reduce existing radiation risks[2]. Due to the uncertainty associated with the results obtained with this test method, test samples requiring more accurate test results can be measured using high purity germanium (HPGe) detectors gamma-ray spectrometry in a testing laboratory, following appropriate preparation of the test samples[15][16]. This document does not contain criteria to establish the activity concentration of OILs.
- Standard22 pagesEnglish languagesale 15% off
- Standard23 pagesFrench languagesale 15% off
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 0,07 MeV to 1,2 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, 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.
- Standard50 pagesEnglish languagesale 10% offe-Library read for1 day
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 MeV and 3,6 MeV maximum beta energy corresponding to 0,07 MeV to 1,2 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 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 applicable to two series of reference beta 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.
- Standard29 pagesEnglish languagesale 10% offe-Library read for1 day
This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the operational quantities for radiation protection purposes defined by the International Commission on Radiation Units and Measurements (ICRU). However, as noted in ICRU 56, 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.
- Standard27 pagesEnglish languagesale 10% offe-Library read for1 day
This document applies to the determination of beta emitters activity concentration using liquid scintillation counting. The method requires the preparation of a scintillation source, which is obtained by mixing the test sample and a scintillation cocktail. The test sample can be liquid (aqueous or organic), or solid (particles or filter or planchet).
NOTE Planchet are samples, described in 8.5, out of solid material e.g. small metal, plastic or glass pans or support material made of these materials
This document describes the conditions for measuring the activity concentration of beta emitter radionuclides by liquid scintillation counting[2].
The choice of the test method using liquid scintillation counting involves the consideration of the potential presence of other beta-, alpha- and gamma emitter radionuclides in the test sample. In this case, a specific sample treatment by separation or extraction is implemented to isolate the radionuclide of interest in order to avoid any interference with other beta-, alpha- and gamma-emitting radionuclides during the counting phase.
This document is applicable to all types of liquid samples having an activity concentration ranging from about 1 Bq·l−1 to 106 Bq·l−1. For a liquid test sample, it is possible to dilute liquid test samples in order to obtain a solution having an activity compatible with the measuring instrument. For solid samples, the activity of the prepared scintillation source shall be compatible with the measuring instrument.
The measurement range is related to the test method used: nature of test portion, preparation of the scintillator - test portion mixture, measuring assembly as well as to the presence of the co-existing activities due to interfering radionuclides.
Test portion preparations (such as distillation for 3H measurement, or benzene synthesis for 14C measurement, etc.) are outside the scope of this document and are described in specific test methods using liquid scintillation[3][[4][5][6][7][8][9][10].
- Standard31 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies methods to determine 226Ra by alpha spectrometry in supply water, drinking water, rainwater, surface and ground water, marine water, as well as cooling water, industrial water, domestic, and industrial wastewater after proper sampling, handling and test sample preparation. The detection limit depends on the sample volume, the instrument used, the background count rate, the detection efficiency, the counting time and the chemical yield. The detection limit of the methods described in this document, using currently available alpha spectrometry apparatus, is equal to or lesser than 3 mBq·l−1 (or mBq·kg−1), which is lower than the WHO criteria for safe consumption of drinking water (1 Bq·l−1)[ REF Reference_ref_12 \r \h 4 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000110000005200650066006500720065006E00630065005F007200650066005F00310032000000 ]. This value can typically be achieved with a counting time of 48 h for a test sample volume of 40 ml. The method described in this document is applicable in the event of an emergency situation. Filtration of the test sample is necessary for the methods described in this document if suspended solids are present. The analysis of 226Ra adsorbed to suspended matter is not covered by this method, because it requires a mineralization step. 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.
- Standard31 pagesEnglish languagesale 15% off
- Standard31 pagesFrench languagesale 15% off
This document applies to the determination of beta emitters activity concentration using liquid scintillation counting. The method requires the preparation of a scintillation source, which is obtained by mixing the test sample and a scintillation cocktail. The test sample can be liquid (aqueous or organic), or solid (particles or filter or planchet).
NOTE Planchet are samples, described in 8.5, out of solid material e.g. small metal, plastic or glass pans or support material made of these materials
This document describes the conditions for measuring the activity concentration of beta emitter radionuclides by liquid scintillation counting[2].
The choice of the test method using liquid scintillation counting involves the consideration of the potential presence of other beta-, alpha- and gamma emitter radionuclides in the test sample. In this case, a specific sample treatment by separation or extraction is implemented to isolate the radionuclide of interest in order to avoid any interference with other beta-, alpha- and gamma-emitting radionuclides during the counting phase.
This document is applicable to all types of liquid samples having an activity concentration ranging from about 1 Bq·l−1 to 106 Bq·l−1. For a liquid test sample, it is possible to dilute liquid test samples in order to obtain a solution having an activity compatible with the measuring instrument. For solid samples, the activity of the prepared scintillation source shall be compatible with the measuring instrument.
The measurement range is related to the test method used: nature of test portion, preparation of the scintillator - test portion mixture, measuring assembly as well as to the presence of the co-existing activities due to interfering radionuclides.
Test portion preparations (such as distillation for 3H measurement, or benzene synthesis for 14C measurement, etc.) are outside the scope of this document and are described in specific test methods using liquid scintillation[3][[4][5][6][7][8][9][10].
- Standard31 pagesEnglish languagesale 10% offe-Library read for1 day
This document applies to the determination of beta emitters activity concentration using liquid scintillation counting. The method requires the preparation of a scintillation source, which is obtained by mixing the test sample and a scintillation cocktail. The test sample can be liquid (aqueous or organic), or solid (particles or filter or planchet). NOTE Planchet are samples, described in REF Section_sec_8.5 \r \h 8.5, out of solid material e.g. small metal, plastic or glass pans or support material made of these materials This document describes the conditions for measuring the activity concentration of beta emitter radionuclides by liquid scintillation counting[ REF Reference_ref_8 \r \h 2 08D0C9EA79F9BACE118C8200AA004BA90B0200000008000000100000005200650066006500720065006E00630065005F007200650066005F0038000000 ]. The choice of the test method using liquid scintillation counting involves the consideration of the potential presence of other beta-, alpha- and gamma emitter radionuclides in the test sample. In this case, a specific sample treatment by separation or extraction is implemented to isolate the radionuclide of interest in order to avoid any interference with other beta-, alpha- and gamma-emitting radionuclides during the counting phase. This document is applicable to all types of liquid samples having an activity concentration ranging from about 1 Bq·l−1 to 106 Bq·l−1. For a liquid test sample, it is possible to dilute liquid test samples in order to obtain a solution having an activity compatible with the measuring instrument. For solid samples, the activity of the prepared scintillation source shall be compatible with the measuring instrument. The measurement range is related to the test method used: nature of test portion, preparation of the scintillator - test portion mixture, measuring assembly as well as to the presence of the co-existing activities due to interfering radionuclides. Test portion preparations (such as distillation for 3H measurement, or benzene synthesis for 14C measurement, etc.) are outside the scope of this document and are described in specific test methods using liquid scintillation[3][[4][5][6][7][8][9][10].
- Standard22 pagesEnglish languagesale 15% off
- Standard22 pagesFrench languagesale 15% off
IEC 62232:2025 provides methods for the determination of RF field strength, power density and specific absorption rate (SAR) in the vicinity of base stations (BS) for the purpose of evaluating human exposure.
This document:
a) considers intentionally radiating BS which transmit on one or more antennas using one or more frequencies in the range 110 MHz to 300 GHz;
b) considers the impact of ambient sources on RF exposure at least in the 100 kHz to 300 GHz frequency range;
c) specifies the methods to be used for RF exposure evaluation for compliance assessment applications, namely:
1) product compliance – determination of compliance boundary information for a BS product before it is placed on the market;
2) product installation compliance – determination of the total RF exposure levels in accessible areas from a BS product and other relevant sources before the product is put into operation;
3) in-situ RF exposure assessment – measurement of in-situ RF exposure levels in the vicinity of a BS installation after the product has been taken into operation;
d) specifies how to perform RF exposure assessment based on the actual maximum approach;
e) describes several RF field strength, power density, and SAR measurement and computation methodologies with guidance on their applicability to address both the in-situ evaluation of installed BS and laboratory-based evaluations;
f) describes how surveyors establish their specific evaluation procedures appropriate for their evaluation purpose;
g) provides guidance on how to report, interpret and compare results from different evaluation methodologies and, where the evaluation purpose requires it, determine a justified decision against a limit value;
h) provides methods for the RF exposure assessment of BS using time-varying beam-steering technologies such as new radio (NR) BS using massive multiple input multiple output (MIMO).
NOTE 1 Practical implementation case studies are provided as examples in the companion Technical Report IEC TR 62669 [5].
NOTE 2 Although the current BS product types have been specified to operate up to 200 GHz (see, for example, [6] and [7]), the upper frequency of 300 GHz is consistent with applicable exposure limits.
NOTE 3 The lower frequency considered for ambient sources, 100 kHz, is derived from ICNIRP-1998 [2] and ICNIRP-2020 [1]. However, some applicable exposure guidelines require ambient fields to be evaluated as low as 3 kHz, e.g. Safety Code 6 [4] and IEEE Std C95.1-2019 [3].
NOTE 4 Specification of appropriate RF exposure mitigation measures such as signage, access control, and training are beyond the scope of this document. It is possible to refer to the applicable regulations or recommended practices on these topics.
NOTE 5 While this document is based on the current international consensus about the best engineering practice for assessing the compliance of RF exposure with the applicable exposure limits, it is possible that national regulatory agencies specify different requirements. The entity conducting an RF exposure assessment needs to be aware of the applicable regulations.
This fourth edition cancels and replaces the third edition published in 2022. It includes corrections of obvious errors and text improvements on the third edition in order to bring more clarity in the description of the assessment methods and avoid misinterpretations. This edition has the same technical content as the third edition.
- Standard349 pagesEnglish languagesale 10% offe-Library read for1 day
IEC 62232:2025 provides methods for the determination of RF field strength, power density and specific absorption rate (SAR) in the vicinity of base stations (BS) for the purpose of evaluating human exposure. This document: a) considers intentionally radiating BS which transmit on one or more antennas using one or more frequencies in the range 110 MHz to 300 GHz; b) considers the impact of ambient sources on RF exposure at least in the 100 kHz to 300 GHz frequency range; c) specifies the methods to be used for RF exposure evaluation for compliance assessment applications, namely: 1) product compliance – determination of compliance boundary information for a BS product before it is placed on the market; 2) product installation compliance – determination of the total RF exposure levels in accessible areas from a BS product and other relevant sources before the product is put into operation; 3) in-situ RF exposure assessment – measurement of in-situ RF exposure levels in the vicinity of a BS installation after the product has been taken into operation; d) specifies how to perform RF exposure assessment based on the actual maximum approach; e) describes several RF field strength, power density, and SAR measurement and computation methodologies with guidance on their applicability to address both the in-situ evaluation of installed BS and laboratory-based evaluations; f) describes how surveyors establish their specific evaluation procedures appropriate for their evaluation purpose; g) provides guidance on how to report, interpret and compare results from different evaluation methodologies and, where the evaluation purpose requires it, determine a justified decision against a limit value; h) provides methods for the RF exposure assessment of BS using time-varying beam-steering technologies such as new radio (NR) BS using massive multiple input multiple output (MIMO). NOTE 1 Practical implementation case studies are provided as examples in the companion Technical Report IEC TR 62669 [5]. NOTE 2 Although the current BS product types have been specified to operate up to 200 GHz (see, for example, [6] and [7]), the upper frequency of 300 GHz is consistent with applicable exposure limits. NOTE 3 The lower frequency considered for ambient sources, 100 kHz, is derived from ICNIRP-1998 [2] and ICNIRP-2020 [1]. However, some applicable exposure guidelines require ambient fields to be evaluated as low as 3 kHz, e.g. Safety Code 6 [4] and IEEE Std C95.1-2019 [3]. NOTE 4 Specification of appropriate RF exposure mitigation measures such as signage, access control, and training are beyond the scope of this document. It is possible to refer to the applicable regulations or recommended practices on these topics. NOTE 5 While this document is based on the current international consensus about the best engineering practice for assessing the compliance of RF exposure with the applicable exposure limits, it is possible that national regulatory agencies specify different requirements. The entity conducting an RF exposure assessment needs to be aware of the applicable regulations. This fourth edition cancels and replaces the third edition published in 2022. It includes corrections of obvious errors and text improvements on the third edition in order to bring more clarity in the description of the assessment methods and avoid misinterpretations. This edition has the same technical content as the third edition.
- Standard349 pagesEnglish languagesale 10% offe-Library read for1 day
Identical adoption of future IEC/IEEE 63184 into EN IEC/IEEE 63184
- Standard151 pagesEnglish languagesale 10% offe-Library read for1 day
IEC 62232:2025 provides methods for the determination of RF field strength, power density and specific absorption rate (SAR) in the vicinity of base stations (BS) for the purpose of evaluating human exposure.
This document:
a) considers intentionally radiating BS which transmit on one or more antennas using one or more frequencies in the range 110 MHz to 300 GHz;
b) considers the impact of ambient sources on RF exposure at least in the 100 kHz to 300 GHz frequency range;
c) specifies the methods to be used for RF exposure evaluation for compliance assessment applications, namely:
1) product compliance – determination of compliance boundary information for a BS product before it is placed on the market;
2) product installation compliance – determination of the total RF exposure levels in accessible areas from a BS product and other relevant sources before the product is put into operation;
3) in-situ RF exposure assessment – measurement of in-situ RF exposure levels in the vicinity of a BS installation after the product has been taken into operation;
d) specifies how to perform RF exposure assessment based on the actual maximum approach;
e) describes several RF field strength, power density, and SAR measurement and computation methodologies with guidance on their applicability to address both the in-situ evaluation of installed BS and laboratory-based evaluations;
f) describes how surveyors establish their specific evaluation procedures appropriate for their evaluation purpose;
g) provides guidance on how to report, interpret and compare results from different evaluation methodologies and, where the evaluation purpose requires it, determine a justified decision against a limit value;
h) provides methods for the RF exposure assessment of BS using time-varying beam-steering technologies such as new radio (NR) BS using massive multiple input multiple output (MIMO).
NOTE 1 Practical implementation case studies are provided as examples in the companion Technical Report IEC TR 62669 [5].
NOTE 2 Although the current BS product types have been specified to operate up to 200 GHz (see, for example, [6] and [7]), the upper frequency of 300 GHz is consistent with applicable exposure limits.
NOTE 3 The lower frequency considered for ambient sources, 100 kHz, is derived from ICNIRP-1998 [2] and ICNIRP-2020 [1]. However, some applicable exposure guidelines require ambient fields to be evaluated as low as 3 kHz, e.g. Safety Code 6 [4] and IEEE Std C95.1-2019 [3].
NOTE 4 Specification of appropriate RF exposure mitigation measures such as signage, access control, and training are beyond the scope of this document. It is possible to refer to the applicable regulations or recommended practices on these topics.
NOTE 5 While this document is based on the current international consensus about the best engineering practice for assessing the compliance of RF exposure with the applicable exposure limits, it is possible that national regulatory agencies specify different requirements. The entity conducting an RF exposure assessment needs to be aware of the applicable regulations.
This fourth edition cancels and replaces the third edition published in 2022. It includes corrections of obvious errors and text improvements on the third edition in order to bring more clarity in the description of the assessment methods and avoid misinterpretations. This edition has the same technical content as the third edition.
- Standard738 pagesEnglish and French languagesale 15% off
The purpose of this document is to set out the general principles pertaining to the sampling strategy, to the collection and conditioning of samples, to their transport to the laboratory and to the pre-treatment operations to be carried out prior to analysis. It is intended for the use of organisations that implement a sampling programme as well as organisations responsible for collecting samples of bioindicators. These principles are not directly applicable to accident or post-accident situations. These principles can apply to biological matrices in the environment.
- Standard17 pagesEnglish languagesale 15% off
- Standard17 pagesFrench languagesale 15% off
Identical adoption of future IEC/IEEE 63184 into EN IEC/IEEE 63184
- Standard151 pagesEnglish languagesale 10% offe-Library read for1 day
IEC/IEEE 63184:2025 specifies methods to assess human exposure to electromagnetic fields generated by stationary wireless power transfer (WPT) in terms of specific absorption rate (SAR), internal electric fields[1] or current density, and contact currents. The frequency range covered by this document is from 3 kHz to 30 MHz. This document focuses on exposures from inductive WPT systems and specifies:
general compliance assessment procedures; measurement methods; computational assessment methods and assessment combining measurement and computational methods.
This document does not consider the immunity of cardiac implantable electrical devices to radiated disturbances from WPT systems.
This first edition of IEC/IEEE 63184 cancels and replaces the first edition of IEC PAS 63184 published in 2021. This edition constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous edition:
a) lower frequency bound changed from 1 kHz to 3 kHz;
b) clarified contact currents as indirect effects in assessment procedures;
c) in measurement methods applied the formulas of SAR and internal electric field;
d) in computational assessment methods added specifications for averaging of current density and internal E-field;
e) updated uncertainty of computational methods;
f) introduced test reporting contents guidance.
- Standard300 pagesEnglish and French languagesale 15% off
This document specifies a method to determine radium-226 (226Ra) activity concentration in all types of water by coprecipitation followed by gamma-ray spectrometry (see ISO 20042[7]).
The method covers the measurement of soluble 226Ra activity concentrations greater than 0,002 Bq·l−1 using a sample volume of up to 100 l of any water type.
For water samples with a volume of less than a volume of 1 l, direct gamma-ray spectrometry can be performed following ISO 10703 but with a higher detection limit. The typical detection limit for samples of 1 l to 5 l is in the range of 0,002 to 0,000 40 Bq·l−1[8].
NOTE This test method can be adapted to determine other naturally occurring isotopes of radium, such as 223Ra, 224Ra and 228Ra, if the respective ingrowth periods are taken into account.
- Standard23 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies a method to determine radium-226 (226Ra) activity concentration in all types of water by coprecipitation followed by gamma-ray spectrometry (see ISO 20042[7]).
The method covers the measurement of soluble 226Ra activity concentrations greater than 0,002 Bq·l−1 using a sample volume of up to 100 l of any water type.
For water samples with a volume of less than a volume of 1 l, direct gamma-ray spectrometry can be performed following ISO 10703 but with a higher detection limit. The typical detection limit for samples of 1 l to 5 l is in the range of 0,002 to 0,000 40 Bq·l−1[8].
NOTE This test method can be adapted to determine other naturally occurring isotopes of radium, such as 223Ra, 224Ra and 228Ra, if the respective ingrowth periods are taken into account.
- Standard23 pagesEnglish languagesale 10% offe-Library read for1 day
IEC TR 63424-1:2024 describes the methods for validating dynamic power control and (dynamic) exposure time-averaging (DPC-ETA) algorithms used in RF modem chipsets of wireless devices. The DPC-ETA implementations are exposure-based, where SAR is time-averaged according to power recorded by the RF modem. Time-averaging windows up to six minutes consistent with applicable SAR limits and regulatory policies are considered for frequencies up to 6 GHz. The DPC-ETA power control parameters are established based on SAR compliance results with all relevant design and operating tolerances taken into consideration. The device output power is controlled by DPC-ETA to maintain SAR compliance in real-time. While SAR compliance is evaluated independently by applying IEC/IEEE 62209-1528:2020 [1] , this document contains information for algorithm validation.
Quasi-static and dynamic power control test sequences are described in this document for algorithm validation. The test sequences are sent from a radio communication tester (RCT) and DPC-ETA responses are measured with conducted and radiated power measurement methods to confirm algorithm functionality. Test sequences for wireless configurations that need validation, including wireless mode transitions, call drop, handover, discontinuous transmission, and simultaneous transmission are described. Considerations for measurement automation to acquire time-aligned results for correlation with power changes in the test sequences are provided. DPC-ETA algorithms are validated by correlating the normalized power measurement results with the expected behaviours of an implementation for the applied test sequences. The procedures in this document also support algorithm validation of modular transmitters using an appropriate test platform. Guidance for using SAR methods in place of radiated power measurements and capacitive proximity sensor triggering with time-averaged detection are also included.
NOTE 1 A separate document will be considered to validate DPC-ETA implementations above 6 GHz, according to near-field millimetre-wave band power density exposure requirements. Substantially shorter time-averaging window durations, on the order of a few seconds, can be required to satisfy some national regulatory requirements.
NOTE 2 The scope of this document is limited to cellular network technologies that have RF modem transmission power dictated by a base station and therefore can be tested using RCT test sequences. Cellular network technologies (also referred to as wireless wide area networks (WWAN)) include Global System for Mobile Communications (GSM), Universal Mobile Telecommunication System (UMTS), Long-Term Evolution (LTE) and 5G New Radio (NR), including other related 2G, 3G, 4G, and 5G specifications, respectively. A separate document will be considered for validating DPC-ETA implementations for wireless local area network (WLAN) technologies, such as those based on the IEEE 802.11 standards series. With WLAN technologies, the transmit power is dictated independently by the RF modem and can be specific to each power control implementation, requiring different testing approaches.
NOTE 3 The procedures in this document can also be considered for 3GPP [2] 5G NR FR1 bands above 6 GHz.
NOTE 4 This document does not address algorithm validation for simultaneous transmission configurations involving transmitters that are not controlled by DPC-ETA operations in the RF modem. These are evaluated according to regulatory requirements.
- Technical report99 pagesEnglish languagesale 15% off
This document specifies a method to determine radium-226 (226Ra) activity concentration in all types of water by coprecipitation followed by gamma-ray spectrometry (see ISO 20042[7]). The method covers the measurement of soluble 226Ra activity concentrations greater than 0,002 Bq·l−1 using a sample volume of up to 100 l of any water type. For water samples with a volume of less than a volume of 1 l, direct gamma-ray spectrometry can be performed following ISO 10703 but with a higher detection limit. The typical detection limit for samples of 1 l to 5 l is in the range of 0,002 to 0,000 40 Bq·l−1[8]. NOTE This test method can be adapted to determine other naturally occurring isotopes of radium, such as 223Ra, 224Ra and 228Ra, if the respective ingrowth periods are taken into account.
- Standard15 pagesEnglish languagesale 15% off
- Standard15 pagesFrench languagesale 15% off
This document specifies a method to determine thorium 232 (232Th) by inductively coupled plasma mass spectrometry (ICP-MS). The mass concentrations obtained can be converted into activity concentrations. The method described in this document 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. The limit of detection depends on the sample volume, the instrument used, the background count rate, the detection efficiency and the chemical yield. In this document, the limit of detection of the method using currently available apparatus is approximately 2 mBq·l−1 (or mBq·kg−1), which is lower than the WHO criteria for safe consumption of drinking water (1 Bq·l−1)[4]. The method described in this document covers the measurement of 232Th in water at activity concentrations between 2 mBq·l−1 and 5 Bq·l−1. Samples with higher activity concentrations than 5 Bq·l−1 can be measured if a dilution is performed. The method described in this document is applicable in the event of an emergency situation. Filtration of the test sample is necessary for the method described in this document. The analysis of 232Th adsorbed to suspended matter is not covered by this method. The analysis of the insoluble fraction requires a mineralization step that is not covered by this document. In this case, the measurement is made on the different phases obtained. It is the user’s responsibility to ensure the validity of this test method for the water samples tested.
- Standard18 pagesEnglish languagesale 15% off
- Standard19 pagesFrench languagesale 15% off
This document specifies methods to determine strontium-90 (90Sr) by inductively coupled plasma mass spectrometry (ICP-MS). The mass concentrations obtained can be converted into activity concentrations. The method described in this document is applicable to test samples of supply water, 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. The limit of detection depends on the sample volume, the instrument used, the background count rate, the detection efficiency and the chemical yield. In this document, the limit of detection of the method using currently available apparatus and chemical pre-concentration, is approximately 5 Bq·l−1, which is lower than the WHO criteria for safe consumption of drinking water (10 Bq·l−1)[4]. The method described in this document covers the measurement of 90Sr in water at activity concentrations up to 1 000 Bq·l−1. Samples with higher activity concentrations than 1 000 Bq·l−1 can be measured if a dilution is performed. The method described in this document is applicable in the event of an emergency situation. Filtration of the test sample is necessary for the method described in this document. The analysis of 90Sr adsorbed to suspended matter is not covered by this method. The analysis of the insoluble fraction requires a mineralization step that is not covered by this document. In this case, the measurement is made on the different phases obtained. It is the user’s responsibility to ensure the validity of this test method for the water samples tested.
- Standard22 pagesEnglish languagesale 15% off
- Standard23 pagesFrench languagesale 15% off
This document specifies a method to determine 93Zr by inductively coupled plasma mass spectrometry (ICP-MS). The mass concentrations obtained can be converted into activity concentrations. 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. The limit of detection depends on the sample volume, the instrument used, the background count rate, the detection efficiency and the chemical yield. In this document, the limit of detection of the method using currently available apparatus is approximately 0,09 Bq·l−1 (or Bq·kg−1), which is lower than the WHO criteria for safe consumption of drinking water (100 Bq·l−1)[4]. The method described in this document covers the measurement of 93Zr in water at activity concentrations between 0,09 Bq·l−1 and 100 Bq·l−1. Samples with higher activity concentrations than 100 Bq·l−1 can be measured if a dilution is performed. The method described in this document is applicable in the event of an emergency. Filtration of the test sample is necessary for the method described in this document. The analysis of 93Zr adsorbed to suspended matter is not covered by this method. The analysis of the insoluble fraction requires a mineralization step that is not covered by this document. In this case, the measurement is made on the different phases obtained. It is the user’s responsibility to ensure the validity of this test method for the water samples tested.
- Standard17 pagesEnglish languagesale 15% off
This document specifies a method to determine 231Pa by inductively coupled plasma mass spectrometry (ICP-MS). The mass concentrations obtained can be converted into activity concentrations. The method described in this document 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. The limit of detection depends on the sample volume, the instrument used, the background count rate, the detection efficiency and the chemical yield. In this document, the limit of detection of the method using currently available apparatus is approximately 0,1 Bq·l−1 (or Bq·kg−1), which is the same as the WHO criteria for safe consumption of drinking water (0,1 Bq·l−1)[4]. The method described in this document covers the measurement of 231Pa in water at activity concentrations between 0,1 Bq·l−1 and 100 Bq·l−1. Samples with higher activity concentrations than 100 Bq·l−1 can be measured if a dilution is performed. The method described in this document is applicable in the event of an emergency. Filtration of the test sample is necessary for the method described in this document. The analysis of 231Pa adsorbed to suspended matter is not covered by this method. The analysis of the insoluble fraction requires a mineralization step that is not covered by this document. In this case, the measurement is made on the different phases obtained. It is the user’s responsibility to ensure the validity of this test method for the water samples tested.
- Standard18 pagesEnglish languagesale 15% off
IEC 63391:2024 applies to security screening systems that utilize active millimetre-wave (MMW) imaging to inspect persons who are not inside vehicles, containers, or enclosures. Specifically, this document applies to systems used to detect objects carried on the body of the individual being screened at a security checkpoint. This document applies to systems that screen people using radiation in the range between 3 GHz and 150 GHz (100 mm to 2 mm).
This document specifies the technical requirements, test methods, and signage of the active MMW systems for security screening of humans.
This document does not specify minimum or baseline requirements of image quality, automated threat recognition (ATR) performance, nor does it specify a minimum detection time
- Standard22 pagesEnglish languagesale 15% off
This document describes a generic test method for measuring alpha emitting radionuclides, for all types of samples (soil, sediment, construction material, foodstuff, water, airborne, environmental bio-indicator, human biological samples as urine, faeces etc.) by alpha spectrometry. This method can be used for any type of environmental study or monitoring of alpha emitting radionuclides activities. If relevant, this test method requires appropriate sample pre-treatment followed by specific chemical separation of the test portion in order to obtain a thin source proper to alpha spectrometry measurement. This test method can be used to determine the activity, specific activity or activity concentration of a sample containing alpha emitting radionuclides such as 210Po, 226Ra, 228Th, 229Th, 230Th, 232Th, 232U,234U, 235U, 238U, 238Pu, 239+240Pu, 241Am or 243+244Cm. This test method can be used to measure very low levels of activity, one or two orders of magnitude less than the usual natural levels of alpha emitting radionuclides. Annexes B of UNSCEAR 2000 and UNSCEAR 2008 (References [4] and [5]) give, respectively, typical natural activity concentrations for air, foods, drinking waters and, soils and building materials. The detection limit of the test method depends on the amount of the sample material analysed (mass or volume) after concentration, chemical yield, thickness of measurement source and counting time. The quantity of the sample to be collected and analysed depends on the expected activity of the sample and the detection limit to achieve.
- Standard37 pagesEnglish languagesale 15% off
- Standard38 pagesFrench languagesale 15% off
IEC 61674:2024 specifies the performance and some related constructional requirements of DIAGNOSTIC DOSIMETERS intended for the measurement of AIR KERMA, AIR KERMA LENGTH PRODUCT or AIR KERMA RATE, in photon radiation fields used in medical X-ray imaging, such as RADIOGRAPHY, RADIOSCOPY and COMPUTED TOMOGRAPHY (CT), for X-RADIATION with generating potentials in the range of 20 kV to 150 kV. This document is applicable to the performance of DOSIMETERS with VENTED IONIZATION CHAMBERS and/or SEMICONDUCTOR DETECTORS as used in X-ray diagnostic imaging.
IEC 61674:2024 cancels and replaces the second edition published in 2012. This edition constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous edition:
a) for mammography, the manufacturer specifies the REFERENCE VALUE for the RADIATION QUALITY;
b) for mammography, the manufacturer provides the MINIMUM RATED RANGE of RADIATION QUALITIES for the compliance test on energy dependence of response;
c) the compliance test for analogue displays was removed;
d) the compliance tests for range reset, the effect of leakage and recombination losses were removed. These tests are already covered by the test on linearity and cannot be conducted for modern devices. The estimation of COMBINED STANDARD UNCERTAINTY was changed accordingly;
e) the compliance test for mains rechargeable and battery-operated dosimeters were updated for modern devices
- Standard39 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides guidance for those who calibrate protection-level dosemeters and doserate meters for area and individual monitoring with reference neutron radiation fields. This includes the determination of the response as a function of neutron energy and angle of incidence. The operational quantities recommended in ICRU Report 51 are considered. In addition to the description of procedures, this document includes appropriate definitions and conversion coefficients and provides guidance on the statement of measurement uncertainties.
- Standard18 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the general requirements, based on ISO 11074 and ISO/IEC 17025, for all steps in the planning (desk study and area reconnaissance) of the sampling and the preparation of samples for testing. It includes the selection of the sampling strategy, the outline of the sampling plan, the presentation of general sampling methods and equipment, as well as the methodology of the pre-treatment of samples adapted to the measurements of the activity of radionuclides in soil including granular materials of mineral origin which contain NORM or artificial radionuclides, such as sludge, sediment, construction debris, solid waste of different type and materials from technologically enhanced naturally occurring radioactive materials (mining, coal combustion, phosphate fertilizer production etc.).
- Standard38 pagesEnglish languagesale 10% offe-Library read for1 day
This document describes a test method to determine the activity concentration of atmospheric tritium by trapping tritium in air by bubbling through a water solution.
The formulae are given for a sampling system with four bubblers. They can also be applied to trapping systems with only one trapping module consisting of two bubblers if only tritiated water vapour (HTO) is in the atmosphere to be sampled.
This document does not cover laboratory test sample results, in becquerel per litre of trapping solution, according to ISO 9698 or ISO 13168.
The test method detection limit result is between 0,2 Bq∙m-3 and 0,5 Bq∙m-3 when the sampling duration is about one week.
- Standard44 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides guidance for
— the sampling process of the aerosol particles in the air using filter media. This document takes into account the specific behaviour of aerosol particles in ambient air.
— Two methods for sampling procedures with subsequent or simultaneous measurement:
— the determination of the activity concentration of radionuclides bound to aerosol particles in the air knowing the activity deposited in the filter;
— the operating use of continuous air monitoring devices used for real time measurement.
This document describes the test method to determine activity concentrations of radionuclides bound to aerosol particles after air sampling passing through a filter media designed to trap aerosol particles. The method can be used for any type of environmental study or monitoring.
This document does not cover the details of measurement test techniques (gamma spectroscopy, global alpha and beta counting, liquid scintillation, alpha spectrometry) used to determine the activity deposited in the media filter, which are either based on existing standards or internal methods developed by the laboratory in charge of those measurements. Also, this document does not cover the variability of the aerosol particle sizes as given by the composition of the dust contained in ambient air. This document does not address to sampling of radionuclides bound to aerosol particles in the effluent air of nuclear facilities [see ISO 2889:2021].
- Standard54 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the general requirements, based on ISO 11074 and ISO/IEC 17025, for all steps in the planning (desk study and area reconnaissance) of the sampling and the preparation of samples for testing. It includes the selection of the sampling strategy, the outline of the sampling plan, the presentation of general sampling methods and equipment, as well as the methodology of the pre-treatment of samples adapted to the measurements of the activity of radionuclides in soil including granular materials of mineral origin which contain NORM or artificial radionuclides, such as sludge, sediment, construction debris, solid waste of different type and materials from technologically enhanced naturally occurring radioactive materials (mining, coal combustion, phosphate fertilizer production etc.).
- Standard38 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides guidance for
— the sampling process of the aerosol particles in the air using filter media. This document takes into account the specific behaviour of aerosol particles in ambient air.
— Two methods for sampling procedures with subsequent or simultaneous measurement:
— the determination of the activity concentration of radionuclides bound to aerosol particles in the air knowing the activity deposited in the filter;
— the operating use of continuous air monitoring devices used for real time measurement.
This document describes the test method to determine activity concentrations of radionuclides bound to aerosol particles after air sampling passing through a filter media designed to trap aerosol particles. The method can be used for any type of environmental study or monitoring.
This document does not cover the details of measurement test techniques (gamma spectroscopy, global alpha and beta counting, liquid scintillation, alpha spectrometry) used to determine the activity deposited in the media filter, which are either based on existing standards or internal methods developed by the laboratory in charge of those measurements. Also, this document does not cover the variability of the aerosol particle sizes as given by the composition of the dust contained in ambient air. This document does not address to sampling of radionuclides bound to aerosol particles in the effluent air of nuclear facilities [see ISO 2889:2021].
- Standard54 pagesEnglish languagesale 10% offe-Library read for1 day