13.280 - Radiation protection
ICS 13.280 Details
Radiation protection
Strahlenschutz
Protection contre les rayonnements
Varstvo pred sevanjem
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ISO 19238:2014 provides criteria for quality assurance and quality control, evaluation of the performance, and the accreditation of biological dosimetry by cytogenetic service laboratories.
ISO 19238:2014 addresses
a) the confidentiality of personal information, for the customer and the service laboratory,
b) the laboratory safety requirements,
c) the calibration sources and calibration dose ranges useful for establishing the reference dose-effect curves that contribute to the dose estimation from chromosome aberration frequency and the minimum resolvable doses,
d) the scoring procedure for unstable chromosome aberrations used for biological dosimetry,
e) the criteria for converting a measured aberration frequency into an estimate of absorbed dose,
f) the reporting of results,
g) the quality assurance and quality control,
h) informative annexes containing sample instructions for customer, sample questionnaire, sample of report, fitting of the low dose-response curve by the method of maximum likelihood and calculating the error of dose estimate, odds ratio method for cases of suspected exposure to a low dose, and sample data sheet for recording aberrations.
- Standard38 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft35 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides criteria for quality assurance and quality control, evaluation of the performance and the accreditation of biological dosimetry by cytogenetic service laboratories using the dicentric assay performed with manual scoring. This document is applicable to a) the confidentiality of personal information, for the requestor and the service laboratory, b) the laboratory safety requirements, c) the calibration sources and calibration dose ranges useful for establishing the reference dose-response curves that contribute to the dose estimation from unstable chromosome aberration frequency and the detection limit, d) the scoring procedure for unstable chromosome aberrations used for biological dosimetry, e) the criteria for converting a measured aberration frequency into an estimate of absorbed dose, f) the reporting of results, g) the quality assurance and quality control, and h) informative annexes containing sample instructions for requestor (see Annex A), sample questionnaire (see Annex B), sample report (see Annex C), fitting of the low dose-response curve by the method of maximum likelihood and calculating the error of the dose estimate (see Annex D), odds ratio method for cases of suspected exposure to a low dose (see Annex E), a method for determining the decision threshold and detection limit (see Annex F) and sample data sheet for recording aberrations (see Annex G).
- Standard39 pagesEnglish languagesale 15% off
- Standard41 pagesFrench languagesale 15% off
This document specifies methods and means of monitoring for inadvertent movement and illicit trafficking of radioactive material. It provides guidelines on the use of both stationary and portable, for example hand-held, instruments to monitor for radiation signatures from radioactive material. Emphasis is placed on the operational aspects, i.e., requirements derived for monitoring of traffic and commodities mainly at border-crossing facilities. Although the term border is used repeatedly in this document, it is meant to apply not only to international land borders but also maritime ports, airports, and similar locations where goods or individuals are being checked. This document does not specifically address the issue of detection of radioactive materials at recycling facilities, although it is recognized that transboundary movement of metals for recycling occurs, and that monitoring of scrap metals might be done at the borders of a state. This document is applicable to — regulatory bodies and other competent authorities seeking guidance on implementation of action plans to combat illicit trafficking, — law enforcement agencies, for example border guards, to obtain guidelines on recommended monitoring procedures, — equipment manufacturers in order to understand minimum requirements derived from operational necessities according to this document, and — end-users of radiation detection equipment applicable to this document.
- Standard24 pagesEnglish languagesale 15% off
This document provides methodology and criteria to qualify the dosimetry system at workplaces where
it is used. The criteria in this document apply to dosimetry systems which do not meet the criteria with
regard to energy and direction dependent responses described in ISO 21909-1.
The qualification of the dosimetry system at workplace aims to demonstrate that:
— either, the non-conformity of the dosimetry system to some of the requirements on the energy or
direction dependent responses defined in ISO 21909-1 does not lead to significant discrepancies in
the dose determination for a certain workplace field;
— or, that the correction factor or function used for this specific studied workplace enables the
dosimetry system to accurately determine the conventional dose value with uncertainties similar
to the ones given in ISO 21909-1.
The methodologies to characterize the work place field in order to perform the qualification of the
dosimetry system are given in Annex A. Annex B is complementary as it gives the practical methods to
follow, once one methodology is chosen.
The provider of the dosimetry system shall provide the type test results corresponding to ISO 21909-1.
However, when the dosimetry system to be qualified does not comply with all the criteria of ISO 21909-1
dealing with the energy and angle dependence of the response, some tests of the ISO 21909-1 can be not
performed.
- Standard40 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft37 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides performance and test requirements for determining the acceptability of
neutron dosimetry systems to be used for the measurement of personal dose equivalent, Hp(10), for
neutrons ranging in energy from thermal to 20 MeV1).
This document applies to all passive neutron detectors that can be used within a personal dosemeter
in part or in all of the above-mentioned neutron energy range. No distinction between the different
techniques available in the marketplace is made in the description of the tests. Only generic distinctions,
for instance, as disposable or reusable dosemeters, are considered.
This document describes type tests only. Type tests are made to assess the basic characteristics of the
dosimetry systems and are often ensured by recognized national laboratories
This document does not present performance tests for characterizing the degradation induced by the
following:
— intrinsic temporal variability of the quality of the dosemeter supplied by the manufacturer;
— intrinsic temporal variability of preparation treatments (before irradiation and/or before reading),
if existing;
— intrinsic temporal variability of reading process;
— degradation due to environmental effects on the preparation treatments, if existing;
— degradation due to environmental effects on the reading process.
- Standard53 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft50 pagesEnglish languagesale 10% offe-Library read for1 day
IEC 62822-3:2023 applies to equipment for resistance welding and allied processes designed for occupational use by professionals and for use by laymen.
More generally, this document covers equipment for which the welding current flows in an electrical circuit whose geometry cannot be changed and regardless of the technology of the current generator (for example LF-AC, MF-DC for spot or seam welding or capacitive discharge used for stud welding).
This second edition cancels and replaces the first edition published in 2017. This edition constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous edition:
a) inclusion of the uncertainties in the results of the assessment;
b) simplification of the methods of exposure assessment.
- Standard72 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft64 pagesEnglish languagesale 10% offe-Library read for1 day
The following documents, in whole or in part, are normatively referenced in ISO 20785-3:2015 and are indispensable for its application. For dated references, only the edition cited applies. For undated references, the latest edition of the referenced document (including any amendments) applies.
ISO/IEC Guide 98‑1, Uncertainty of measurement ? Part 1: Introduction to the expression of uncertainty in measurement
ISO/IEC Guide 98‑3, Uncertainty of measurement ? Part 3: Guide to the expression of uncertainty in measurement (GUM:1995)
ISO 20785‑1, Dosimetry for exposures to cosmic radiation in civilian aircraft ? Part 1: Conceptual basis for measurements
ISO 20785‑2, Dosimetry for exposures to cosmic radiation in civilian aircraft ? Part 2: Characterization of instrument response
- Standard26 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft22 pagesEnglish languagesale 10% offe-Library read for1 day
This document describes a test method for the determination of radon-222 (222Rn) activity concentration in non-saline waters by extraction and liquid scintillation counting.
The 222Rn activity concentrations, which can be measured by this test method utilizing currently available instruments, are above 0,5 Bq·l−1 which is the typical detection limit for a 10 ml test sample and a measuring time of 1 h.
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.
- Draft21 pagesEnglish languagesale 10% offe-Library read for1 day
This document sets forth performance-based criteria and recommendations for the design and use of systems for sampling of airborne radioactive materials in the effluent air from the ducts and stacks of nuclear facilities. The requirements and recommendations of this document are aimed at sampling that is conducted for regulatory compliance and system control. If existing air-sampling systems are not designed to the performance requirements and recommendations of this document, an evaluation of the performance of the system is advised. If deficiencies are discovered, a determination of whether or not a retrofit is needed and practicable is recommended. It can be impossible to meet the requirements of this document in all conditions with a sampling system designed for normal operations only. Under off-normal conditions, the criteria or recommendations of this document still apply. However, for accident conditions, special accident air sampling systems or measurements can be used. This document does not address outdoor air sampling, radon measurements, or the surveillance of airborne radioactive substances in the workplace of nuclear facilities. NOTE Reference [1] addresses the instrumentation that is frequently used in nuclear air monitoring. Reference [5] addresses air sampling in the workplace of nuclear facilities. References [6] and [7] describe the performance characteristics of air monitors.
- Standard115 pagesEnglish languagesale 15% off
- Standard123 pagesFrench languagesale 15% off
- Draft116 pagesEnglish languagesale 15% off
- Draft116 pagesEnglish languagesale 15% off
This document describes a test method for the determination of radon-222 (222Rn) activity concentration in non-saline waters by extraction and liquid scintillation counting. The 222Rn activity concentrations, which can be measured by this test method utilizing currently available instruments, are above 0,5 Bq·l−1 which is the typical detection limit for a 10 ml test sample and a measuring time of 1 h. 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.
- Standard16 pagesEnglish languagesale 15% off
- Standard17 pagesFrench languagesale 15% off
- Draft18 pagesFrench languagesale 15% off
This document provides performance and test requirements for determining the acceptability of
neutron dosimetry systems to be used for the measurement of personal dose equivalent, Hp(10), for
neutrons ranging in energy from thermal to 20 MeV1).
This document applies to all passive neutron detectors that can be used within a personal dosemeter
in part or in all of the above-mentioned neutron energy range. No distinction between the different
techniques available in the marketplace is made in the description of the tests. Only generic distinctions,
for instance, as disposable or reusable dosemeters, are considered.
This document describes type tests only. Type tests are made to assess the basic characteristics of the
dosimetry systems and are often ensured by recognized national laboratories
This document does not present performance tests for characterizing the degradation induced by the
following:
— intrinsic temporal variability of the quality of the dosemeter supplied by the manufacturer;
— intrinsic temporal variability of preparation treatments (before irradiation and/or before reading),
if existing;
— intrinsic temporal variability of reading process;
— degradation due to environmental effects on the preparation treatments, if existing;
— degradation due to environmental effects on the reading process.
- Standard53 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft50 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides methodology and criteria to qualify the dosimetry system at workplaces where
it is used. The criteria in this document apply to dosimetry systems which do not meet the criteria with
regard to energy and direction dependent responses described in ISO 21909-1.
The qualification of the dosimetry system at workplace aims to demonstrate that:
— either, the non-conformity of the dosimetry system to some of the requirements on the energy or
direction dependent responses defined in ISO 21909-1 does not lead to significant discrepancies in
the dose determination for a certain workplace field;
— or, that the correction factor or function used for this specific studied workplace enables the
dosimetry system to accurately determine the conventional dose value with uncertainties similar
to the ones given in ISO 21909-1.
The methodologies to characterize the work place field in order to perform the qualification of the
dosimetry system are given in Annex A. Annex B is complementary as it gives the practical methods to
follow, once one methodology is chosen.
The provider of the dosimetry system shall provide the type test results corresponding to ISO 21909-1.
However, when the dosimetry system to be qualified does not comply with all the criteria of ISO 21909-1
dealing with the energy and angle dependence of the response, some tests of the ISO 21909-1 can be not
performed.
- Standard40 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft37 pagesEnglish languagesale 10% offe-Library read for1 day
These international guidelines are based on the assumption that monitoring of environmental components (atmosphere, water, soil and biota) as well as food quality is performed to ensure the protection of human health[5][7][8][9][10][11][12]. The guidelines constitute a basis for the setting of national regulations, standards, and inter alia, for monitoring air, water and food in support of public health, specifically to protect the public from ionizing radiation. This document provides: — guidance to collect data needed for the assessment of human exposure to radionuclides naturally present or discharged by anthropogenic activities in the different environmental compartments (atmosphere, waters, soils, biota) and food; — guidance on the environmental characterization needed for the prospective and/or retrospective dose assessment methods of public exposure; — guidance that addresses actions appropriate for an event involving uncontrolled releases of gamma-emitters (e.g. nuclear power reactor emergencies) and also events that would involve beta- or alpha-emitters would require additional consideration of the pathways, instrumentation, laboratory analysis, operational intervention levels, protective actions, etc., appropriate to their release; — guidance for staff in nuclear installations responsible for the preparation of radiological assessments in support of permit or authorization applications and National Authorities’ officers in charge of the assessment of doses to the public for the purposes of determining gaseous or liquid effluent radioactive discharge authorizations; — information to the public on the parameters used to conduct a dose assessment for any exposure situations to a representative person/population. It is important that the dose assessment process be transparent, and that assumptions are clearly understood by stakeholders who can participate in, for example, the selection of habits of the representative person to be considered. This document refers to various published ISO documents. When appropriate, this document also refers to national standards or other publicly available documents.
- Standard33 pagesEnglish languagesale 15% off
- Draft35 pagesEnglish languagesale 15% off
This document specifies a test method for measuring actinides (238Pu, 239+240Pu, 241Am, 242Cm, 243+244Cm and 237Np) in water samples by alpha spectrometry following a chemical separation. This method can be used for any type of environmental study or monitoring after appropriate sampling and handling, and test sample preparation. The detection limit of the test method is 5 × 10−3 Bq·l-1 to 5 × 10−4 Bq·l-1 for a volume of test portion between 0,1 l to 5 l with a counting time of two to ten days. This is lower than the WHO criteria for safe consumption of drinking water (1 Bq·l-1 or 10 Bq·l-1 depending on radionuclide).[4] The method described in this document is applicable in the event of an emergency situation.
- Standard29 pagesEnglish languagesale 15% off
- Standard30 pagesFrench languagesale 15% off
- Draft29 pagesEnglish languagesale 15% off
- Draft29 pagesEnglish languagesale 15% off
This document gives the basis for the measurement of ambient dose equivalent at flight altitudes for the evaluation of the exposures to cosmic radiation in civilian aircraft.
- Standard26 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft22 pagesEnglish languagesale 10% offe-Library read for1 day
This document gives the basis for the measurement of ambient dose equivalent at flight altitudes for the evaluation of the exposures to cosmic radiation in civilian aircraft.
- Standard17 pagesEnglish languagesale 15% off
- Standard19 pagesFrench languagesale 15% off
- Draft18 pagesFrench languagesale 15% off
This document applies to the testing of the decontamination of textiles, which are contaminated by radioactive materials. The test method describes the technique to assess the efficiency of decontamination agents (see ISO 7503‑1 and ISO 7503‑3). This document applies to the testing of detergents, which may be used in aqueous solutions for the purpose of cleaning radioactively contaminated textiles. The radionuclides used in this test are those commonly found in the nuclear industry (60Co and 137Cs or 134Cs) in aqueous form. The test can also be adapted for use with other radionuclides and other chemical forms, depending on the customer requirements, if the solutions are chemically stable and do not damage the test specimen. The test method is not suitable if the radionuclide emits low energy gamma rays, like 55Fe, or low energy beta or alpha particles that are readily attenuated in the textile fabrics, or if the nuclide has a chemical or isotopic interaction with the detergent used in the method (e.g. tritium which could be in several chemical forms). The test method does not apply to the testing of the ability of detergents to remove non-radioactive dirt.
- Standard28 pagesEnglish languagesale 15% off
- Standard28 pagesEnglish languagesale 15% off
- Standard30 pagesFrench languagesale 15% off
This document specifies general requirements for proficiency tests that are offered to in vivo bioassay measurement facilities operating a whole-body counter (WBC) or partial body counter (PBC) for monitoring of persons. It specifies minimum requirements for proficiency testing applicable to dosimetry laboratories that have dedicated facilities for in vivo monitoring and where accreditation is required as part of providing the service. It also provides general requirements for proficiency testing that may include a larger group of non-accredited laboratories that may perform measurements as part of worker surveillance or in response to an emergency. This document covers proficiency tests that involve only the quantification of radionuclides and tests that require the identification of radionuclides and their activity. This document does not define specific requirements on administrative aspects of proficiency testing, such as shipping and finance, that may be the subject of national or international regulation.
- Standard13 pagesEnglish languagesale 15% off
- Standard14 pagesFrench languagesale 15% off
IEC 61098:2023 applies to contamination monitors that include warning assembles and meters used for the monitoring of radioactive contamination on the surface of personnel whether they be clothed or not. The document is applicable only to that type of equipment where the user stays at the monitor. This document is applicable to the monitoring of the whole body (including the head), hands and feet, but parts of this document can be used for monitors designed for the monitoring of radioactive contamination on the hands and/or feet only. This document does not include tritium measurement.
This third edition cancels and replaces the second edition published in 2003. This edition includes the following significant technical changes with respect to the previous edition:
a. Title is modified.
b. As an alternative of small area sources, area sources are added to be used for methods of test with respect to the variation of response with source position, effective instrument efficiency, detection limit (DL), and variation of response with energy.
c. Detection limit (DL) complies with the ISO 11929 series.
d. Descriptions of influence quantities of type F and type S are added.
e. Consistency with IEC 62706 is promoted for environmental requirements, mechanical requirements, electromagnetic compatibility and methods of test.
f. Descriptions of overhead detectors are added.
g. Descriptions of friskers are added with respect to the hand and foot monitoring.
h. Figures are made easier to understand the relation between the detector position and the response, and the positional relation between the detector surface and the source.
- Standard143 pagesEnglish and French languagesale 15% off
This International Standard applies to the BASIC SAFETY and ESSENTIAL PERFORMANCE of both FIXED and MOBILE X-RAY EQUIPMENT declared by the MANUFACTURER to be suitable for RADIOSCOPICALLY GUIDED INTERVENTIONAL PROCEDURES, hereafter referred to as INTERVENTIONAL X-RAY EQUIPMENT. Its scope excludes, in particular:
- equipment for RADIOTHERAPY;
- equipment for COMPUTED TOMOGRAPHY;
- ACCESSORIES intended to be introduced into the PATIENT;
- mammographic X-RAY EQUIPMENT;
- dental X-RAY EQUIPMENT.
NOTE 1 Examples of RADIOSCOPICALLY GUIDED INTERVENTIONAL PROCEDURES, for which the use of INTERVENTIONAL X-RAY EQUIPMENT complying with this standard is recommended, are given in Annex AA.
NOTE 2 Specific requirements for magnetic navigation devices, and for the use of INTERVENTIONAL X-RAY EQUIPMENT in an operating room environment were not considered in this particular standard; therefore no specific requirements have been developed for these devices or uses. In any case, such devices or uses remain under the general clause requirements.
NOTE 3 INTERVENTIONAL X-RAY EQUIPMENT, when used for cone-beam CT mode, is covered by this standard and not by IEC 60601-2-44 [2]2. No additional requirements for operation in cone-beam CT mode were identified for this standard (see also Note 4 in 203.6.4.5).
INTERVENTIONAL X-RAY EQUIPMENT declared by the MANUFACTURER to be suitable for RADIOSCOPICALLY GUIDED INTERVENTIONAL PROCEDURES, which does not include a PATIENT SUPPORT as part of the system, is exempt from the PATIENT SUPPORT provisions of this standard.
If a clause or subclause is specifically intended to be applicable to INTERVENTIONAL X-RAY EQUIPMENT only, or to ME SYSTEMS only, the title and content of that clause or subclause will say so. If that is not the case, the clause or subclause applies both to INTERVENTIONAL X-RAY EQUIPMENT and to ME SYSTEMS, as relevant.
NOTE 4 See also 4.2 of the general standard.
The subclauses of this standard supersede IEC 60601-2-54 subclauses. IEC 60601-2-54 applies only with regards to the cited subclauses; non-cited subclauses of IEC 60601-2-54 do not apply.
- Standard65 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft59 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the characteristics of fume cupboards, as defined in EN 14175-1, for work with unsealed radioactive materials with specific requirements regarding radiation protection. It does not apply to fume cupboards, glove boxes or hot cells (shielded radiation containment cells which can incorporate fume extraction).
The purpose of this document is to set out rules for the design and testing of fume cupboards for work with unsealed radioactive materials, in order to provide guidelines for the manufacturer, planner, installer, operator, assessor and the authorities.
This document only covers bench type fume cupboards.
- Standard18 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft15 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the different leakage test methods for sealed sources. It gives a comprehensive set of procedures using radioactive and non-radioactive means.
This document applies to the following situations:
— leakage testing of test sources following design classification testing in accordance with ISO 2919[1];
— production quality control testing of sealed sources;
— periodic inspections of the sealed sources performed at regular intervals, during the working life.
Annex A of this document gives guidance to the user in the choice of the most suitable method(s) according to situation and source type.
It is recognized that there can be circumstances where special tests, not described in this document, are required.
It is emphasized, however, that insofar as production, use, storage and transport of sealed radioactive sources are concerned, compliance with this document is no substitute for complying with the requirements of the relevant IAEA regulations[17] and other relevant national regulations. It is also recognized that countries can enact statutory regulations which specify exemptions for tests, according to sealed source type, design, working environment, and activity (e.g., for very low activity reference sources where the total activity is less than the leakage test limit).
- Standard22 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft23 pagesEnglish languagesale 10% offe-Library read for1 day
The primary purpose of this document is to provide minimum acceptable criteria required to establish a procedure for retrospective dosimetry by electron paramagnetic resonance spectroscopy and to report the results.
The second purpose is to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories.
This document covers the determination of absorbed dose in the measured material. It does not cover the calculation of dose to organs or to the body. It covers measurements in both biological and inanimate samples, and specifically:
a) based on inanimate environmental materials like glass, plastics, clothing fabrics, saccharides, etc., usually made at X-band microwave frequencies (8 GHz to 12 GHz);
b) in vitro tooth enamel using concentrated enamel in a sample tube, usually employing X-band frequency, but higher frequencies are also being considered;
c) in vivo tooth dosimetry, currently using L-band (1 GHz to 2 GHz), but higher frequencies are also being considered;
d) in vitro nail dosimetry using nail clippings measured principally at X-band, but higher frequencies are also being considered;
e) in vivo nail dosimetry with the measurements made at X-band on the intact finger or toe;
f) in vitro measurements of bone, usually employing X-band frequency, but higher frequencies are also being considered.
For biological samples, in vitro measurements are carried out in samples after their removal from the person or animal and under laboratory conditions, whereas the measurements in vivo are carried out without sample removal and may take place under field conditions.
NOTE The dose referred to in this document is the absorbed dose of ionizing radiation in the measured materials.
- Standard27 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft24 pagesEnglish languagesale 10% offe-Library read for1 day
The purpose of this document is to provide minimum criteria required for quality assurance and quality control, evaluation of the performance and to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories applying ex vivo X-band EPR spectroscopy with human tooth enamel.
This document covers the determination of absorbed dose in tooth enamel (hydroxyapatite). It does not cover the calculation of dose to organs or to the body.
This document addresses:
a) responsibilities of the customer and laboratory;
b) confidentiality and ethical considerations;
c) laboratory safety requirements;
d) the measurement apparatus;
e) preparation of samples;
f) measurement of samples and EPR signal evaluation;
g) calibration of EPR dose response;
h) dose uncertainty and performance test;
i) quality assurance and control.
- Standard31 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft28 pagesEnglish languagesale 10% offe-Library read for1 day
This document focuses on monitoring the activity concentrations of radioactive gases. They allow the calculation of the activity releases, in the gaseous effluent discharge from facilities producing positron emitting radionuclides and radiopharmaceuticals. Such facilities produce short-lived radionuclides used for medical purposes or research and can release gases typically including, but not limited to 18F, 11C, 15O and 13N. These facilities include accelerators, radiopharmacies, hospitals and universities. This document provides performance‑based criteria for the design and use of air monitoring equipment including probes, transport lines, sample monitoring instruments, and gas flow measuring methods. This document also provides information on monitoring program objectives, quality assurance, development of air monitoring control action levels, system optimisation and system performance verification.
The goal of achieving an unbiased measurement is accomplished either by direct (in-line) measurement on the exhaust stream or with samples extracted from the exhaust stream (bypass), provided that the radioactive gases are well mixed in the airstream. This document sets forth performance criteria and recommendations to assist in obtaining valid measurements.
NOTE 1 The criteria and recommendations of this document are aimed at monitoring which is conducted for regulatory compliance and system control. If existing air monitoring systems were not designed according to the performance criteria and recommendations of this document, an evaluation of the performance of the system is advised. If deficiencies are discovered based on a performance evaluation, a determination of the need for a system retrofit is to be made and corrective actions adopted where practicable.
NOTE 2 The criteria and recommendations of this document apply under both normal and off‑normal operating conditions, provided that these conditions do not include production of aerosols or vapours. If the normal and/or off-normal conditions produce aerosols and vapours, then the aerosol collection principles of ISO 2889 also apply.
- Standard62 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft59 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies a methodology to determine indoor gamma dose from building materials and to help classify such a product as required in the Construction Products Regulation (EU 305/2011). With this methodology, the relation between the actual release of radiation and the dose to which inhabitants of a buidling are exposed can be assessed. The method takes into account also the Basic Safety Standards Directive (2013/59/EURATOM).
- Standard28 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft26 pagesEnglish languagesale 10% offe-Library read for1 day
This document focuses on monitoring the activity concentrations of radioactive gases. They allow the calculation of the activity releases, in the gaseous effluent discharge from facilities producing positron emitting radionuclides and radiopharmaceuticals. Such facilities produce short-lived radionuclides used for medical purposes or research and can release gases typically including, but not limited to 18F, 11C, 15O and 13N. These facilities include accelerators, radiopharmacies, hospitals and universities. This document provides performance‑based criteria for the design and use of air monitoring equipment including probes, transport lines, sample monitoring instruments, and gas flow measuring methods. This document also provides information on monitoring program objectives, quality assurance, development of air monitoring control action levels, system optimisation and system performance verification.
The goal of achieving an unbiased measurement is accomplished either by direct (in-line) measurement on the exhaust stream or with samples extracted from the exhaust stream (bypass), provided that the radioactive gases are well mixed in the airstream. This document sets forth performance criteria and recommendations to assist in obtaining valid measurements.
NOTE 1 The criteria and recommendations of this document are aimed at monitoring which is conducted for regulatory compliance and system control. If existing air monitoring systems were not designed according to the performance criteria and recommendations of this document, an evaluation of the performance of the system is advised. If deficiencies are discovered based on a performance evaluation, a determination of the need for a system retrofit is to be made and corrective actions adopted where practicable.
NOTE 2 The criteria and recommendations of this document apply under both normal and off‑normal operating conditions, provided that these conditions do not include production of aerosols or vapours. If the normal and/or off-normal conditions produce aerosols and vapours, then the aerosol collection principles of ISO 2889 also apply.
- Standard62 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft59 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the different leakage test methods for sealed sources. It gives a comprehensive set of procedures using radioactive and non-radioactive means.
This document applies to the following situations:
— leakage testing of test sources following design classification testing in accordance with ISO 2919[1];
— production quality control testing of sealed sources;
— periodic inspections of the sealed sources performed at regular intervals, during the working life.
Annex A of this document gives guidance to the user in the choice of the most suitable method(s) according to situation and source type.
It is recognized that there can be circumstances where special tests, not described in this document, are required.
It is emphasized, however, that insofar as production, use, storage and transport of sealed radioactive sources are concerned, compliance with this document is no substitute for complying with the requirements of the relevant IAEA regulations[17] and other relevant national regulations. It is also recognized that countries can enact statutory regulations which specify exemptions for tests, according to sealed source type, design, working environment, and activity (e.g., for very low activity reference sources where the total activity is less than the leakage test limit).
- Standard22 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft23 pagesEnglish languagesale 10% offe-Library read for1 day
The primary purpose of this document is to provide minimum acceptable criteria required to establish a procedure for retrospective dosimetry by electron paramagnetic resonance spectroscopy and to report the results.
The second purpose is to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories.
This document covers the determination of absorbed dose in the measured material. It does not cover the calculation of dose to organs or to the body. It covers measurements in both biological and inanimate samples, and specifically:
a) based on inanimate environmental materials like glass, plastics, clothing fabrics, saccharides, etc., usually made at X-band microwave frequencies (8 GHz to 12 GHz);
b) in vitro tooth enamel using concentrated enamel in a sample tube, usually employing X-band frequency, but higher frequencies are also being considered;
c) in vivo tooth dosimetry, currently using L-band (1 GHz to 2 GHz), but higher frequencies are also being considered;
d) in vitro nail dosimetry using nail clippings measured principally at X-band, but higher frequencies are also being considered;
e) in vivo nail dosimetry with the measurements made at X-band on the intact finger or toe;
f) in vitro measurements of bone, usually employing X-band frequency, but higher frequencies are also being considered.
For biological samples, in vitro measurements are carried out in samples after their removal from the person or animal and under laboratory conditions, whereas the measurements in vivo are carried out without sample removal and may take place under field conditions.
NOTE The dose referred to in this document is the absorbed dose of ionizing radiation in the measured materials.
- Standard27 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft24 pagesEnglish languagesale 10% offe-Library read for1 day
The purpose of this document is to provide minimum criteria required for quality assurance and quality control, evaluation of the performance and to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories applying ex vivo X-band EPR spectroscopy with human tooth enamel.
This document covers the determination of absorbed dose in tooth enamel (hydroxyapatite). It does not cover the calculation of dose to organs or to the body.
This document addresses:
a) responsibilities of the customer and laboratory;
b) confidentiality and ethical considerations;
c) laboratory safety requirements;
d) the measurement apparatus;
e) preparation of samples;
f) measurement of samples and EPR signal evaluation;
g) calibration of EPR dose response;
h) dose uncertainty and performance test;
i) quality assurance and control.
- Standard31 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft28 pagesEnglish languagesale 10% offe-Library read for1 day
The scope of ISO 16659 series is to provide different test methods aiming at assessing the efficiency of radioactive iodine traps in ventilation systems of nuclear facilities. The ISO 16659 series deals with iodine traps containing a solid sorbent — mainly activated and impregnated charcoal, the most common solid iodine sorbents used in the ventilation systems of nuclear facilities — as well as other sorbents for special conditions (e.g. high temperature zeolites). The scope of this document is to provide general and common requirements for the different test methods for industrial nuclear facilities. The different methods will be described in other specific parts of ISO 16659 series. Nuclear medicine applications are excluded from the scope of ISO 16659 series. In principle, ISO 16659 series is used mainly for filtering radioactive iodine, but other radioactive gases can also be trapped together with iodine. In such a case, some specificity may have to be adapted for these other radioactive gases in specific parts of ISO 16659 series. This document describes the main general requirements in order to check in situ the efficiency of the iodine traps, according to test conditions that are proposed to be as reproducible as possible.
- Standard21 pagesEnglish languagesale 15% off
- Standard24 pagesFrench languagesale 15% off
A water phantom is used to ensure the accurate measurement of absorbed dose delivered by a radiation therapy machine as well as standardizing the dose distribution produced by the radiation therapy device. This document describes a detailed procedure for the construction and calibration of a polystyrene phantom and the results of its use in measuring the absorbed dose profile around the mechanical centre of a radiosurgery medical device, the full width at half maximum (FWHM) of the field and the physical penumbra at the mechanical centre, as well as the associated uncertainties. According to IAEA TRS-483 document, the most common design recommended in Gamma Knife® system is a hemisphere atop a water filled or compact polystyrene cylinder, and when using a polystyrene phantom, the measurement depth of the absorbed dose to water is reported to be the centre of the hemisphere with the radius of 8 cm. This document mainly describes the procedure for measuring the absorbed dose distribution around the mechanical centre of Gamma Knife® and obtaining the FWHM and penumbra from it. The developed phantom is made of polystyrene and has a hemispherical shape in accordance with the design suggested in IAEA TRS-483. This type of phantom is specific and adapted only for the Gamma Knife® radiosurgery facilities (PerfexionTM and IconTM models) and does not apply to general dosimetry protocols in radiotherapy facilities that use a small radiation field to treat a disease such as LINAC or Cyberknife. Considering that the type of medical device corresponds to treatment using external beam radiotherapy following small static fields, this technical report follows the recommendations published in the IAEA TRS‑483.
- Technical report11 pagesEnglish languagesale 15% off
This document 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 62669:2019 [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.
- Standard346 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft318 pagesEnglish languagesale 10% offe-Library read for1 day
IEC 62694:2022 applies to backpack-type radiation detectors (BRDs) that are primarily used for the detection of illicit trafficking of radioactive material. BRDs are portable instruments designed to be worn during use. BRDs detect gamma radiation and may include neutron detection and the ability to identify gamma-ray emitting radionuclides.
This document establishes the operational and testing requirements associated with radiation measurements and the expected electrical, mechanical, and environmental conditions while in use.
This second edition cancels and replaces the first edition, published in 2014. This edition includes the following significant technical changes with respect to the previous edition:
a. making the standard consistent with the new standards for detection of illicit trafficking of radioactive material;
b. creating unformed functionality test for all environmental, electromagnetic and mechanical tests and a requirement for the coefficient of variation of each nominal mean reading;
c. revised radiological requirements including the simplification of radionuclide identification acceptance criteria;
d. reference to IEC 62706 for the environmental, electromagnetic and mechanical test conditions.
- Standard74 pagesEnglish and French languagesale 15% off
IEC 62232:2022 addresses the evaluation of RF field strength, power density and specific absorption rate (SAR) levels in the vicinity of base stations (BS), also called products or equipment under test (EUT), intentionally radiating in the radio frequency (RF) range 110 MHz to 300 GHz in accordance with the scope, see Clause 1. It does not address the evaluation of current density. RF exposure evaluation methods to be used for product compliance, product installation compliance and in-situ RF exposure assessments are specified in this document. Exposure limits are not specified in this document. The entity conducting RF exposure assessments refers to the set of exposure limits applicable where exposure takes place. Examples of applicable exposure limits considered in this document are provided in the Bibliography, for example ICNIRP-2020 [1], ICNIRP-1998 [2], IEEE Std C95.1™-2019 [3] and Safety Code 6 [4].
- Standard346 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft318 pagesEnglish languagesale 10% offe-Library read for1 day
IEC 62618:2022 applies to Spectroscopy-based alarming Personal Radiation Detectors (SPRD). SPRDs detect and identify gamma radiation and may detect neutron radiation. SPRDs can be worn on a belt or in a pocket to alert the wearer of the presence of a radiation source. SPRDs provide search, similar to that of a Personal Radiation Device (PRD), and identification capability to identify radiation sources. They can discriminate between alarms caused by Naturally Occurring Radioactive Materials (NORM) or medical radionuclides and alarms from industrial sources or Special Nuclear Material (SNM).
This document establishes performance requirements and specifies general characteristics, general test conditions, radiological, climatic, mechanical, and electromagnetic characteristics. This document also provides test methods that are used to determine if an SPRD meets the stated requirements.
This second edition cancels and replaces the first edition published in 2013. This edition includes the following significant technical changes with respect to the previous edition:
a. making the standard consistent with the new standards for detection of illicit trafficking of radioactive material (see the Introduction); b. creating unformed functionality test for all environmental, electromagnetic and mechanical tests and a requirement for the coefficient of variation of each nominal mean reading; c. reference to IEC 62706 for the environmental, electromagnetic and mechanical test conditions; d. adding information regarding climatic exposures.
- Standard59 pagesEnglish and French languagesale 15% off
The purpose of this document is to give an overview of the minimum requirements for performing the dicentric assay with quality control measures using mitogen stimulated peripheral blood lymphocytes for initial assessment of individuals involved in a mass casualty scenario. The dicentric assay is the use of chromosome damage to quickly estimate approximate radiation doses received by individuals in order to supplement the early clinical categorization of casualties. This document focuses on the organizational and operational aspects of applying the dicentric assay in an initial assessment mode. The technical aspects of the dicentric assay can be found in ISO 19238. This document is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories (as defined in Clause 7).
- Standard18 pagesEnglish languagesale 15% off
- Standard19 pagesFrench languagesale 15% off
This document applies to all kinds of passive dosimetry systems that are used for measuring:
- the personal dose equivalent Hp(10) (for individual whole body monitoring),
- the personal dose equivalent Hp(3) (for individual eye lens monitoring),
- the personal dose equivalent Hp(0,07) (for whole body skin and local skin for extremity monitoring),
- the ambient dose equivalent H*(10) (for workplace and environmental monitoring),
- the directional dose equivalent H'(3) (for workplace and environmental monitoring), or
- the directional dose equivalent H'(0,07) (for workplace and environmental monitoring).
- Amendment7 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft6 pagesEnglish languagesale 10% offe-Library read for1 day
This document applies to all kinds of passive dosimetry systems that are used for measuring:
- the personal dose equivalent Hp(10) (for individual whole body monitoring),
- the personal dose equivalent Hp(3) (for individual eye lens monitoring),
- the personal dose equivalent Hp(0,07) (for whole body skin and local skin for extremity monitoring),
- the ambient dose equivalent H*(10) (for workplace and environmental monitoring),
- the directional dose equivalent H'(3) (for workplace and environmental monitoring), or
- the directional dose equivalent H'(0,07) (for workplace and environmental monitoring).
- Standard90 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft90 pagesEnglish languagesale 10% offe-Library read for1 day
This document applies to all kinds of passive dosimetry systems that are used for measuring: - the personal dose equivalent Hp(10) (for individual whole body monitoring), - the personal dose equivalent Hp(3) (for individual eye lens monitoring), - the personal dose equivalent Hp(0,07) (for whole body skin and local skin for extremity monitoring), - the ambient dose equivalent H*(10) (for workplace and environmental monitoring), - the directional dose equivalent H'(3) (for workplace and environmental monitoring), or - the directional dose equivalent H'(0,07) (for workplace and environmental monitoring).
- Amendment7 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft6 pagesEnglish languagesale 10% offe-Library read for1 day
IEC 62232:2022 addresses the evaluation of RF field strength, power density and specific absorption rate (SAR) levels in the vicinity of base stations (BS), also called products or equipment under test (EUT), intentionally radiating in the radio frequency (RF) range 110 MHz to 300 GHz in accordance with the scope, see Clause 1. It does not address the evaluation of current density.
RF exposure evaluation methods to be used for product compliance, product installation compliance and in-situ RF exposure assessments are specified in this document. Exposure limits are not specified in this document. The entity conducting RF exposure assessments refers to the set of exposure limits applicable where exposure takes place. Examples of applicable exposure limits considered in this document are provided in the Bibliography, for example ICNIRP-2020 [1], ICNIRP-1998 [2], IEEE Std C95.1™-2019 [3] and Safety Code 6 [4].
- Standard342 pagesEnglish languagesale 15% off
- Standard736 pagesEnglish and French languagesale 15% off
This document applies to all kinds of passive dosimetry systems that are used for measuring: - the personal dose equivalent Hp(10) (for individual whole body monitoring), - the personal dose equivalent Hp(3) (for individual eye lens monitoring), - the personal dose equivalent Hp(0,07) (for whole body skin and local skin for extremity monitoring), - the ambient dose equivalent H*(10) (for workplace and environmental monitoring), - the directional dose equivalent H'(3) (for workplace and environmental monitoring), or - the directional dose equivalent H'(0,07) (for workplace and environmental monitoring).
- Standard90 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft90 pagesEnglish languagesale 10% offe-Library read for1 day
This standard applies to alarming radiation detection instruments that are pocket-sized, carried on the body and used to detect and indicate the presence and general magnitude of gamma radiation fields. Neutron detection may also be provided. Personal Radiation Devices (PRDs) alert the user to the presence of a source of radiation that is distinctly above the measured average local background radiation level. They are not intended to provide a measurement of the ambient or personal dose equivalent rate. This document does not apply to the ambient or personal dose equivalent rate meters which are covered in IEC 60846-1 or IEC 61526, respectively. If the manufacturer states that the PRD can be used for radiation protection purposes, compliance with IEC 60846-1 or IEC 61526 will be needed.
- Standard28 pagesEnglish languagesale 10% offe-Library read for1 day
This standard applies to hand-held instruments used to detect and identify radionuclides and radioactive material, to estimate ambient dose equivalent rate from photon radiation, and optionally, to detect neutron radiation. They are commonly known as radionuclide identification devices or RIDs. This standard does not cover laboratory type, high-resolution photon spectrometers, or instruments covered by IEC 60846-1 (Portable workplace and environmental meters and monitors), IEC 60846-2 (photon dose (rate) meters) or IEC 61005 (neutron dose equivalent (rate) meters).
- Standard37 pagesEnglish languagesale 10% offe-Library read for1 day
This document applies to the design, location and application of installed equipment for
monitoring local gamma radiation dose rates within nuclear facilities during normal operation
and anticipated operational occurrences. High range area gamma radiation dose rate
monitoring equipment for accident conditions currently addressed by IEC 60951-1 and
IEC 60951-3 is not within the scope of this document.
This document does not apply to the measurement of neutron dose rate. Additional equipment
for neutron monitoring may be required, depending on the plant design, if the neutron dose
rate makes a substantial contribution to the total dose equivalent to personnel.
This document provides guidelines for the design principles, the location, the application,
the calibration, the operation, and the testing of installed equipment for continuously
monitoring local gamma radiation dose rates in nuclear facilities under normal operation
conditions and anticipated operational occurrences. These instruments are normally referred
to as area radiation monitors. Portable instruments are also used for this purpose but are not
covered by this document.
Radiation monitors utilized in area radiation monitoring equipment are addressed in
IEC 60532. As discussed in IEC 60532, measurement of gamma radiation may be expressed
by a number of alternative quantities depending on national regulations. However, for this
type of instrument, the most likely quantity to be measured is the air kerma (Gy), or the
ambient dose equivalent H*(10)(Sv).
- Standard27 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft26 pagesEnglish languagesale 10% offe-Library read for1 day
This document defines terms and definitions related to radiological protection concepts in the subject field of nuclear energy, nuclear technology and the different nuclear applications. It is intended to facilitate communication and promote common understanding.
- Standard48 pagesEnglish languagesale 15% off
This document specifies the requirements for personal contamination monitoring and dose assessment following wounds involving radioactive materials. It includes requirements for the direct monitoring at the wound site, monitoring of uptake of radionuclides into the body and assessment of local and systemic doses following the wound event.
It does not address:
— details of monitoring and assessment methods for specific radionuclides;
— monitoring and dose assessment for materials in contact with intact skin or pre-existing wounds, including hot particles;
— therapeutic protocols. However, the responsible entity needs to address the requirements for decontamination and decorporation treatments if appropriate.
- Standard42 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft42 pagesEnglish languagesale 10% offe-Library read for1 day
See the scope of IEC 61031:2020. Adoption of IEC 61031:2020 is to be done without modification.
- Standard27 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft26 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the requirements for personal contamination monitoring and dose assessment following wounds involving radioactive materials. It includes requirements for the direct monitoring at the wound site, monitoring of uptake of radionuclides into the body and assessment of local and systemic doses following the wound event.
It does not address:
— details of monitoring and assessment methods for specific radionuclides;
— monitoring and dose assessment for materials in contact with intact skin or pre-existing wounds, including hot particles;
— therapeutic protocols. However, the responsible entity needs to address the requirements for decontamination and decorporation treatments if appropriate.
- Standard42 pagesEnglish languagesale 10% offe-Library read for1 day
- Draft42 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies fume cupboards for work with unsealed radioactive materials with specific requirements regarding radiation protection and it does not apply to glove boxes or hot cells not even to α emitting radioisotopes.
The purpose of this document is to set out rules for the design and testing of fume cupboards for work with unsealed radioactive materials, in order to provide guidelines for the planner, installer, operator, assessor and the authorities.
NOTE If, when handling unsealed radioactive substances, radiopharmaceuticals are produced for use on humans, the fume cupboards covered by this document are not sufficient.
Before using radioactive materials, a safety assessment needs to be performed. To find the maximum activity allowed for every activity with radioactive material it is necessary to take into account the three principles of radiological protection, namely justification, optimization, and the application of dose limits, clarifying how they apply to radiation sources delivering exposure and to individuals receiving exposure. Shield and abatement system required are also evaluated.
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- Draft15 pagesEnglish languagesale 10% offe-Library read for1 day