13.280 - Radiation protection
ICS 13.280 Details
Radiation protection
Strahlenschutz
Protection contre les rayonnements
Varstvo pred sevanjem
General Information
e-Library Subscription
Create subscription and get permanent access to documents within 13.280 - Radiation protection
Currently subscription includes documents marked with .We are working on making all documents available within the subscription.
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 the applicable requirements related to the design and the operation of confinement and ventilation systems for fusion facilities for tritium fuels and tritium fuel handling facilities specific for fusion applications for peaceful purposes using high tritium inventories, as well as for their specialized buildings such as hot cells, examination laboratories, emergency management centres, radioactive waste treatment and storage facilities.
In most countries, a tritium quantity is declared as high for tritium inventories higher than a range of 10 g to 100 g. In the tritium fusion facilities in the scope of this document, the tritium inventory is deemed to be higher than this range for the whole site.
This document applies especially to confinement and ventilation systems that ensure the safety function of nuclear facilities involved in nuclear fusion with the goal to protect the workers, the public and the environment from the dissemination of radioactive contamination originating from the operation of these installations, and in particular from airborne tritium contamination with adequate confinement systems.
- Standard89 pagesEnglish languagesale 10% offe-Library read for1 day
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).
- Standard27 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides requirements and guidance regarding the use of CAAS for operations of a nuclear facility. Requirements and guidance on CAAS design are provided in the IEC 60860.
This document is applicable to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear establishments.
This document applies when a need for CAAS has been established. Information about the need for CAAS is given in Annex C.
This document does not include details of administrative steps, which are considered to be activities of a robust management system (ISO 14943 provides details of administrative steps).
Details of nuclear accident dosimetry and personnel exposure evaluations are not within the scope of this document.
This document is concerned with gamma and neutron radiation rate-sensing systems. Specific detection criteria can also be met with integrating systems; systems detecting either neutron or gamma radiation can also be used. Equivalent considerations then apply.
- Standard37 pagesEnglish languagesale 10% offe-Library read for1 day
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.
- Standard33 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides procedures for monitoring the dose to the skin, the extremities, and the lens of the eye. It gives guidance on how to decide if such dosemeters are needed and to ensure that individual monitoring is appropriate to the nature of the exposure, taking practical considerations into account.
This document specifies procedures for individual monitoring of radiation exposure of the skin of the body, extremities (skin of the hands, fingers, wrists, forearms including elbow, lower leg including patella, feet and ankles), and lens of the eye in planned exposure situations. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV, electrons and positrons in the range of 0,07 MeV to 1,2 MeV mean beta energies being equivalent to 0,22 MeV and 3,6 MeV beta maximum energy - in accordance to the ISO 6980 series, and neutrons in the range of thermal to 20 MeV.
This document gives guidance for the design of a monitoring programme to ensure compliance with legal individual dose limits. It refers to the appropriate operational dose quantities, and it gives guidance on the type and frequency of individual monitoring and the type and positioning of the dosemeter. Finally, different approaches to assess and analyse skin, extremity, and lens of the eye doses are given.
It is not in the scope of this document to consider exposure due to alpha radiation fields.
NOTE 1 The requirements for the monitoring of the occupational exposure may be given in national regulations.
NOTE 2 Dose to the lens of the eye due to intake of tritium is not in the scope of this document. Moreover, the situation of the workers that work in contaminated atmosphere and can have alpha and/or radon eye lens dose is also not in the scope.
- Standard43 pagesEnglish languagesale 10% offe-Library read for1 day
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).
- Standard27 pagesEnglish languagesale 10% offe-Library read for1 day
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.
- Standard33 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the applicable requirements related to the design and the operation of confinement and ventilation systems for fusion facilities for tritium fuels and tritium fuel handling facilities specific for fusion applications for peaceful purposes using high tritium inventories, as well as for their specialized buildings such as hot cells, examination laboratories, emergency management centres, radioactive waste treatment and storage facilities.
In most countries, a tritium quantity is declared as high for tritium inventories higher than a range of 10 g to 100 g. In the tritium fusion facilities in the scope of this document, the tritium inventory is deemed to be higher than this range for the whole site.
This document applies especially to confinement and ventilation systems that ensure the safety function of nuclear facilities involved in nuclear fusion with the goal to protect the workers, the public and the environment from the dissemination of radioactive contamination originating from the operation of these installations, and in particular from airborne tritium contamination with adequate confinement systems.
- Standard89 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides requirements and guidance regarding the use of CAAS for operations of a nuclear facility. Requirements and guidance on CAAS design are provided in the IEC 60860.
This document is applicable to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear establishments.
This document applies when a need for CAAS has been established. Information about the need for CAAS is given in Annex C.
This document does not include details of administrative steps, which are considered to be activities of a robust management system (ISO 14943 provides details of administrative steps).
Details of nuclear accident dosimetry and personnel exposure evaluations are not within the scope of this document.
This document is concerned with gamma and neutron radiation rate-sensing systems. Specific detection criteria can also be met with integrating systems; systems detecting either neutron or gamma radiation can also be used. Equivalent considerations then apply.
- Standard37 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies requirements concerning safety systems raised by the application of superconducting magnets in fusion facilities. Safety systems include confinement systems (both static and dynamic types), shielding barriers, penetrations, and supporting systems such as instrumentation and control. The requirements are applicable to both normal and abnormal operation of a fusion facility. For instance, the radiation protection shall be adequate in order to permit the hands-on operation to the electronics and parts for inspection, maintenance and replacement; the hazards associated with superconducting magnets, such as the loss of superconductivity (quench), Paschen breakdown following helium and voltage leakage, shall be prevented from breaching the integrity of safety systems. This document will facilitate the design and assessment of the safety systems in a fusion facility with superconducting magnets for all configurations, such as tokamak, stellarator and magneto-inertial fusion devices. Based on the advancement and maturity of the tokamak configuration, this document outlines safety requirements mostly derived from the tokamak configuration but also applicable to other configurations and layouts that may be adopted by future fusion devices.
- Standard19 pagesEnglish languagesale 15% off
This document is applicable to the radiation shielding design and evaluation work for medical proton accelerators of proton energies ranging from 70 MeV to 250 MeV, with subsystems such as beam transport system and nozzle components. The radiation protection recommendations given in this document cover the aspects relating to regulations, shielding design goals and other design criteria, role of the manufacturers, of the radiation protection officer or qualified expert, the medical physicist, the licensee and interactions between them, sources and radiations around a proton accelerator, shielding for accelerators and its subsystems (including shielding materials and transmission values, calculations for various room configurations, duct impact on radiation protection) and the radiological measurements. FLASH proton therapy is not covered by this document. NOTE 1 Annex A provides a list of the most used Monte-Carlo codes for shielding calculation. NOTE 2 Annex B provides the analytical methods and the corresponding necessary data for shielding calculation. NOTE 3 Annex C provides a set of examples on shielding calculation of barriers, maze and skyshine problems. NOTE 4 Annex D provides radiation shielding consideration on special topics.
- Standard49 pagesEnglish languagesale 15% off
This document provides procedures for monitoring the dose to the skin, the extremities, and the lens of the eye. It gives guidance on how to decide if such dosemeters are needed and to ensure that individual monitoring is appropriate to the nature of the exposure, taking practical considerations into account.
This document specifies procedures for individual monitoring of radiation exposure of the skin of the body, extremities (skin of the hands, fingers, wrists, forearms including elbow, lower leg including patella, feet and ankles), and lens of the eye in planned exposure situations. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV, electrons and positrons in the range of 0,07 MeV to 1,2 MeV mean beta energies being equivalent to 0,22 MeV and 3,6 MeV beta maximum energy - in accordance to the ISO 6980 series, and neutrons in the range of thermal to 20 MeV.
This document gives guidance for the design of a monitoring programme to ensure compliance with legal individual dose limits. It refers to the appropriate operational dose quantities, and it gives guidance on the type and frequency of individual monitoring and the type and positioning of the dosemeter. Finally, different approaches to assess and analyse skin, extremity, and lens of the eye doses are given.
It is not in the scope of this document to consider exposure due to alpha radiation fields.
NOTE 1 The requirements for the monitoring of the occupational exposure may be given in national regulations.
NOTE 2 Dose to the lens of the eye due to intake of tritium is not in the scope of this document. Moreover, the situation of the workers that work in contaminated atmosphere and can have alpha and/or radon eye lens dose is also not in the scope.
- Standard43 pagesEnglish languagesale 10% offe-Library read for1 day
This document provides procedures for monitoring the dose to the skin, the extremities, and the lens of the eye. It gives guidance on how to decide if such dosemeters are needed and to ensure that individual monitoring is appropriate to the nature of the exposure, taking practical considerations into account. This document specifies procedures for individual monitoring of radiation exposure of the skin of the body, extremities (skin of the hands, fingers, wrists, forearms including elbow, lower leg including patella, feet and ankles), and lens of the eye in planned exposure situations. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV, electrons and positrons in the range of 0,07 MeV to 1,2 MeV mean beta energies being equivalent to 0,22 MeV and 3,6 MeV beta maximum energy - in accordance to the ISO 6980 series, and neutrons in the range of thermal to 20 MeV. This document gives guidance for the design of a monitoring programme to ensure compliance with legal individual dose limits. It refers to the appropriate operational dose quantities, and it gives guidance on the type and frequency of individual monitoring and the type and positioning of the dosemeter. Finally, different approaches to assess and analyse skin, extremity, and lens of the eye doses are given. It is not in the scope of this document to consider exposure due to alpha radiation fields. NOTE 1 The requirements for the monitoring of the occupational exposure may be given in national regulations. NOTE 2 Dose to the lens of the eye due to intake of tritium is not in the scope of this document. Moreover, the situation of the workers that work in contaminated atmosphere and can have alpha and/or radon eye lens dose is also not in the scope.
- Standard35 pagesEnglish languagesale 15% off
- Standard38 pagesFrench languagesale 15% off
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
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
IEC 60601-2-68:2025 applies to the BASIC SAFETY and ESSENTIAL PERFORMANCE of X-ray based IMAGE-GUIDED RADIOTHERAPY equipment for use with EXTERNAL BEAM EQUIPMENT (EBE). This document covers safety aspects of kilovoltage (kV) and megavoltage (MV) X-ray imaging devices integrated in a specified geometrical relationship with EBE for the purpose of IGRT. It covers aspects of communication and relationships between the EXTERNAL BEAM EQUIPMENT and X-ray imaging devices, attached or not directly attached to, but in the same RADIATION shielded area as, and dedicated for use only with, the EXTERNAL BEAM EQUIPMENT. This document deals with equipment for OFFLINE X-IGRT, ONLINE X-IGRT and REAL-TIME X-IGRT. It covers procedures to reduce the risk of over-reliance on the X-IGRT EBE SYSTEM. For example, in the case of ONLINE X-IGRT, the MANUFACTURER will provide an interactive interface for user interaction with the correction suggested by the system. This document does not apply to CT SCANNERS, X-RAY EQUIPMENT for RADIOGRAPHY, and X-RAY EQUIPMENT for RADIOSCOPY, which are not intended for use for IGRT. Requirements that are being tested according to another standard can be identified by the manufacturer and if equivalent do not require retesting, instead evidence can refer to the CT SCANNER, X-RAY EQUIPMENT for RADIOGRAPHY, or X-RAY EQUIPMENT for RADIOSCOPY EQUIPMENT manufacturer's providing compliance statements or test reports. If the X-IGRT EQUIPMENT is combined with an MEE, any requirement that is the same for the X-IGRT EQUIPMENT and the MEE, such as a PATIENT POSITIONER, is not required to be tested twice, but can be accepted as tested by the MEE. This document applies for X-ray equipment for radiography, radioscopy, and COMPUTER tomography used for IGRT. If a clause or subclause is specifically intended to be applicable to X-IGRT EBE SYSTEMS, the content of that clause or subclause will say so. Where that is not the case, the clause or subclause applies only to X-IGRT EQUIPMENT.
This document, with the inclusion of TYPE TESTS and SITE TESTS, applies respectively to the MANUFACTURER and some installation aspects of X-IGRT EBE SYSTEMS intended to be:
• for NORMAL USE, operated under the authority of the RESPONSIBLE ORGANIZATION by QUALIFIED PERSONS having the required skills for a particular medical application, for particular specified clinical purposes, e.g., STATIONARY RADIOTHERAPY or MOVING BEAM RADIOTHERAPY,
• maintained in accordance with the recommendations given in the INSTRUCTIONS FOR USE, and
• subject to regular quality assurance performance and calibration checks by a QUALIFIED PERSON.
IEC 80601-2-68:2024 cancels and replaces the first edition published in 2014. This edition constitutes a technical revision.
This edition includes the following significant technical changes with respect to the previous edition:
a) alignment with the new editions of the relevant standards:
– IEC 60601-2-1:2020;
– IEC 60601-2-44:2009, IEC 60601-2-44:2009/AMD1:2012 and IEC 60601-2-44:2009/AMD2:2016;
– IEC 60601-2-64:2014;
b) clarification of the use of IEC 60601-2-68 for CT SCANNERS, X-RAY EQUIPMENT for RADIOGRAPHY and RADIOSCOPY used in the same room with an EXTERNAL BEAM EQUIPMENT (EBE);
c) introduction of updated requirements related to MECHANICAL HAZARDS, RADIATION HAZARDS, PROGRAMMABLE ELECTRICAL MEDICAL SYSTEMS (PEMS), ACCOMPANYING DOCUMENTATION of an ME SYSTEM, and REMOTE OPERATION.
- Standard79 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
This document specifies the minimum requirements for the design of programmes to monitor workers exposed to the risk of internal contamination by radioactive material and establishes principles for the development of compatible goals and requirements for monitoring programmes.
This document specifies the
a) purposes of monitoring and monitoring programmes,
b) description of the different categories of monitoring programmes,
c) quantitative criteria for conducting monitoring programmes,
d) suitable monitoring methods and criteria for their selection,
e) information that has to be collected for the design of a monitoring programme,
f) general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties),
g) frequencies of measurements calculated using the ICRP Occupational Intakes of Radionuclides (OIR) series,
h) individual monitoring in specific cases (intake of actinides, intake via a wound and intake through the intact skin),
i) quality assurance, and
j) documentation, reporting and record-keeping.
This document does not apply to
— the monitoring of exposure to radon and its radioactive decay products,
— detailed descriptions of measuring methods and techniques,
— detailed procedures for in vivo measurements and in vitro analysis,
— interpretation of measurements results in terms of dose,
— biokinetic data and mathematical models for converting measured activities into absorbed dose, equivalent dose and effective dose,
— the investigation of the causes or implications of an exposure or intake.
- Standard36 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the minimum requirements for the design of programmes to monitor workers exposed to the risk of internal contamination by radioactive material and establishes principles for the development of compatible goals and requirements for monitoring programmes.
This document specifies the
a) purposes of monitoring and monitoring programmes,
b) description of the different categories of monitoring programmes,
c) quantitative criteria for conducting monitoring programmes,
d) suitable monitoring methods and criteria for their selection,
e) information that has to be collected for the design of a monitoring programme,
f) general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties),
g) frequencies of measurements calculated using the ICRP Occupational Intakes of Radionuclides (OIR) series,
h) individual monitoring in specific cases (intake of actinides, intake via a wound and intake through the intact skin),
i) quality assurance, and
j) documentation, reporting and record-keeping.
This document does not apply to
— the monitoring of exposure to radon and its radioactive decay products,
— detailed descriptions of measuring methods and techniques,
— detailed procedures for in vivo measurements and in vitro analysis,
— interpretation of measurements results in terms of dose,
— biokinetic data and mathematical models for converting measured activities into absorbed dose, equivalent dose and effective dose,
— the investigation of the causes or implications of an exposure or intake.
- Standard36 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the minimum requirements for the design of programmes to monitor workers exposed to the risk of internal contamination by radioactive material and establishes principles for the development of compatible goals and requirements for monitoring programmes. This document specifies the a) purposes of monitoring and monitoring programmes, b) description of the different categories of monitoring programmes, c) quantitative criteria for conducting monitoring programmes, d) suitable monitoring methods and criteria for their selection, e) information that has to be collected for the design of a monitoring programme, f) general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties), g) frequencies of measurements calculated using the ICRP Occupational Intakes of Radionuclides (OIR) series, h) individual monitoring in specific cases (intake of actinides, intake via a wound and intake through the intact skin), i) quality assurance, and j) documentation, reporting and record-keeping. This document does not apply to — the monitoring of exposure to radon and its radioactive decay products, — detailed descriptions of measuring methods and techniques, — detailed procedures for in vivo measurements and in vitro analysis, — interpretation of measurements results in terms of dose, — biokinetic data and mathematical models for converting measured activities into absorbed dose, equivalent dose and effective dose, — the investigation of the causes or implications of an exposure or intake.
- Standard27 pagesEnglish languagesale 15% off
- Standard30 pagesFrench languagesale 15% off
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
ISO 7503 (all parts) and ISO 8769 are addressed to the people responsible for determining the radioactivity present on solid surfaces. ISO 7503 is published in three parts and can be used jointly or separately according to needs.
ISO 7503-1:2016 relates to the assessment of surface contamination by direct and indirect measurements and the calibration of the associated instrumentation.
The standard applies to alpha-, beta- and photon emitters and is intended for use by hospitals, universities, police, or industrial establishments. The standard also can be used in the assessment of activity on trucks, containers, parcels, equipment and is applicable in any organization which handles radioactive materials. Generally, it is applicable to well defined flat surfaces where direct methods are applicable, however, it can also be used for surfaces which are not flat and where indirect wipe tests would be appropriate. These investigations may be carried out on containers, inaccessible areas, non-flat areas where wipe tests can be used. This part of ISO 7503 may be useful in emergency situations, i.e. in nuclear accidents where health physics professionals would be involved.
ISO 7503-1:2016 does not apply to the evaluation of contamination of the skin, of clothing and of loose material such as gravel.
NOTE The test method using wipe-test samples for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-2. The calibration of instruments for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-3.
- Standard31 pagesEnglish languagesale 10% offe-Library read for1 day
- Standard26 pagesEnglish languagesale 15% off
- Standard26 pagesEnglish languagesale 15% off
- Standard28 pagesFrench languagesale 15% off
- Standard – translation29 pagesSlovenian languagesale 10% offe-Library read for1 day
ISO 3999:2004 specifies the performance, design and test requirements of apparatus for gamma radiography with portable, mobile and fixed exposure containers of the various categories defined in Clause 4.
It applies to apparatus designed to allow the controlled use of gamma radiation emitted by a sealed radioactive source for industrial radiography purposes, in order that persons will be safeguarded when the apparatus is used in conformity with the regulations in force regarding radiation protection.
It is emphasised, however, that so far as transport of apparatus and sealed radioactive source is concerned, compliance with ISO 3999:2004 is no substitute for satisfying the requirements of relevant international transport regulations (IAEA Regulations for the safe transport of radioactive materials: IAEA-STI-PUB 998, Safety Standards Series ST-1 and ST-2, and/or the relevant national transport regulations).
The operational use of apparatus for industrial gamma radiography is not covered by ISO 3999:2004. Users of this equipment shall comply with national regulations and codes of practice.
- Standard36 pagesEnglish languagesale 10% offe-Library read for1 day
- Standard32 pagesEnglish languagesale 15% off
- Standard33 pagesFrench languagesale 15% off
- Standard – translation35 pagesSlovenian languagesale 10% offe-Library read for1 day
ISO 7503 (all parts) and ISO 8769 are addressed to the people responsible for measuring the radioactivity present on solid surfaces.
ISO 7503-2:2016 applies to the evaluation of contamination on surfaces in terms of activity per unit area by an indirect method of measurement.
ISO 7503-2:2016 is applicable to well-defined surfaces, such as those of equipment and facilities, containers of radioactive materials, sealed sources and buildings or land.
ISO 7503-2:2016 can be used for laboratory and equipment/installation control and for remediation and monitoring activities to comply with release criteria.
ISO 7503-2:2016 also refers to institutions/authorities controlling nuclear material transports or material/equipment clearance according to national legislation guideline values or international convention limits.
ISO 7503-2:2016 does not apply to contamination of the skin, clothing or loose material, such as gravel.
NOTE Direct evaluation of surface contamination from alpha-emitters, beta-emitters and photon emitters is dealt with in ISO 7503-1. The calibration of instruments for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-3.
- Standard16 pagesEnglish languagesale 10% offe-Library read for1 day
- Standard16 pagesEnglish languagesale 10% offe-Library read for1 day
- Standard11 pagesEnglish languagesale 15% off
- Standard12 pagesFrench languagesale 15% off
- Standard – translation15 pagesSlovenian languagesale 10% offe-Library read for1 day
This document specifies the action spectrum for photocarcinogenesis of non-melanoma skin cancers.
- Standard9 pagesEnglish languagesale 15% off
- Amendment13 pagesEnglish languagesale 10% offe-Library read for1 day
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 applies to the testing of surfaces that may become contaminated by radioactive materials. The ease of decontamination is a property of a surface and an important criterion for selecting surface materials used in the nuclear industry, interim storage or disposal facilities from which contamination can be removed easily and rapidly without damaging the surface. The test described in this document is a rapid laboratory-based method to compare the ease of decontamination of different surface materials. The results from the test can be one parameter to take into account when selecting surface coatings such as varnish or impervious layers such as ceramics and other surfaces. The radionuclides used in this test are those commonly found in the nuclear industry (137Cs, 134Cs and 60Co) in aqueous form. The test can also be adopted for use with other radionuclides and other chemical forms, depending on the customer requirements, if the solutions are chemically stable and do not corrode the test specimen. The test does not measure the ease of decontamination of the surface materials in practical use, as this depends on the radionuclide(s) present, their chemical form, the duration of exposure to the contaminant and the environmental conditions amongst other factors. The test method is not intended to describe general decontamination procedures or to assess the efficiency of decontamination procedures (see ISO 7503-1 to ISO 7503-3). The test method is not suitable for use of radiochemicals if the radionuclide emits low energy gamma rays or beta particles that are readily attenuated in the surface.
- Standard34 pagesEnglish languagesale 15% off
- Standard34 pagesFrench languagesale 15% off
IEC 62709:2024 applies to security screening systems that utilize X-ray radiation and are used to inspect people who are not inside vehicles, containers, or enclosures. Specifically, this document applies to systems used to detect objects carried on or within the body of the individual being inspected. The objective is to provide standard methods of measuring and reporting imaging quality characteristics that enable system manufacturers, potential system users and other interested parties to:
a) Establish a consistent indicator of the expected technical performance of screening systems used for the inspection of individuals. Such technical performance testing complements explicit detection testing and evaluation. In this document "detection" refers to items in an image.
b) Provide repeatable and verifiable imaging performance data that can be used to compare systems from different vendors.
c) Establish a baseline that can be used over time to calibrate the system or detect any performance degradation. (It is not intended that the entire test method be employed for daily quality assurance testing.)
d) Establish minimum acceptable performance requirements for the systems described above.
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) Clarified the test procedures to maintain consistency with IEC 62463.
b) Changed the term "spatial resolution" to "pentalith resolution".
c) Modified some standard test conditions.
d) Modified some terms and definitions.
e) Changed the imaging requirements for transmission general-use systems.
- Standard43 pagesEnglish languagesale 15% off
- Standard89 pagesEnglish languagesale 15% off
This document specifies the dosimetric and organizational criteria and the test procedures to be used for the periodic verification of the performance of dosimetry services supplying personal and/or area, i.e. workplace and/or environmental, dosemeters used for individual (personal) and/or area, i.e. workplace and/or environmental monitoring.
NOTE The quality of a supplier of a dosimetry service depends on both the characteristics of the approved (type‑tested) dosimetry system and the training and experience of the staff, together with the calibration procedures and quality assurance programmes.
The performance evaluation according to this document can be carried out by a dosimetry service to demonstrate the fulfilment of specified performance requirements. The irradiation qualities used in this document are representative for exposure situations that are expected or mimic workplace fields from the radiological activities being monitored using the dosemeters from the services.
This document applies to personal and area dosemeters for the assessment of external photon radiation with a fluence-weighted mean energy between 8 keV and 10 MeV, beta radiation with a fluence-weighted mean energy between 60 keV and 1,2 MeV, and neutron radiation with a fluence-weighted mean energy between 25,3 meV, i.e. thermal neutrons with a Maxwellian energy distribution with kT = 25,3 meV, and 200 MeV.
It covers all types of personal and area dosemeters needing laboratory processing (e.g. thermoluminescent, optically stimulated luminescence, radiophotoluminescent, track detectors or photographic-film dosemeters) and involving continuous measurements or measurements repeated regularly at fixed time intervals (e.g. several weeks, one month).
Active direct reading as well as semi-passive or hybrid dosemeters, such as direct ion storage (DIS) or silicon photomultiplier (SiPM) dosemeters, for dose measurement, can also be treated according to this document. Then, they are treated as if they were passive, i.e. the dosimetry service reads their indicated values and reports them to the evaluation organization.
In this document, the corrected indicated (corrected indication) value is the one given by the dosimetry systems as the final result of the evaluation algorithm (for example display of the software, printout) in units of dose equivalent (Sv).
Environmental dosemeters usually indicate the quantity H*(10) but they can, in addition or alternatively, indicate the quantity H'(3), H'(0,07), air kerma, Ka, or absorbed dose, D. All these dosemeters can also be treated according to this document. If Ka or D is indicated (in Gy) the dose values in this document stated in Sv shall then be interpreted as equivalent values in Gy.
- Standard26 pagesEnglish languagesale 10% offe-Library read for1 day
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.
- Standard36 pagesEnglish languagesale 10% offe-Library read for1 day
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.
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.
- Standard21 pagesEnglish languagesale 10% offe-Library read for1 day
IEC 62463:2024 is applicable to security screening systems designed to expose persons to X‑rays. In particular, the document applies to systems where the body is exposed to the primary beam of X-rays. It is common to divide currently used systems into three types: backscatter systems, transmission systems and combination backscatter/transmission systems. The purpose of this document is to provide standardized requirements and test methods to ensure the safe operation of X-ray personnel screening systems, from a radiation protection point of view. In particular, the document specifies requirements related to the radiation protection of the persons being screened, persons who are in the vicinity of the equipment and the operators.
This second edition cancels and replaces the first edition published in 2010. This edition includes the following significant technical changes with respect to the previous edition:
a) title modified;
b) the main dose quantity was updated from ambient dose equivalent (H*(10)) to the operational quantities recommended in ICRU Report 95:2020;
c) the scope has been updated from X-ray systems for screening persons to X-ray systems that deliberately expose persons to X-rays for security purposes, which clarifies the ambiguity of whether d) occupied vehicle scanners are within scope;
d) the scheme for classifying systems was changed from one based on whether the system is backscatter, transmission or a combination to a classification system based on the dose level and administrative controls;
e) numerous electrical, environmental, electromagnetic, and mechanical safety requirements were updated.
- Standard26 pagesEnglish 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.
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.
- Standard21 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the dosimetric and organizational criteria and the test procedures to be used for the periodic verification of the performance of dosimetry services supplying personal and/or area, i.e. workplace and/or environmental, dosemeters used for individual (personal) and/or area, i.e. workplace and/or environmental monitoring.
NOTE The quality of a supplier of a dosimetry service depends on both the characteristics of the approved (type‑tested) dosimetry system and the training and experience of the staff, together with the calibration procedures and quality assurance programmes.
The performance evaluation according to this document can be carried out by a dosimetry service to demonstrate the fulfilment of specified performance requirements. The irradiation qualities used in this document are representative for exposure situations that are expected or mimic workplace fields from the radiological activities being monitored using the dosemeters from the services.
This document applies to personal and area dosemeters for the assessment of external photon radiation with a fluence-weighted mean energy between 8 keV and 10 MeV, beta radiation with a fluence-weighted mean energy between 60 keV and 1,2 MeV, and neutron radiation with a fluence-weighted mean energy between 25,3 meV, i.e. thermal neutrons with a Maxwellian energy distribution with kT = 25,3 meV, and 200 MeV.
It covers all types of personal and area dosemeters needing laboratory processing (e.g. thermoluminescent, optically stimulated luminescence, radiophotoluminescent, track detectors or photographic-film dosemeters) and involving continuous measurements or measurements repeated regularly at fixed time intervals (e.g. several weeks, one month).
Active direct reading as well as semi-passive or hybrid dosemeters, such as direct ion storage (DIS) or silicon photomultiplier (SiPM) dosemeters, for dose measurement, can also be treated according to this document. Then, they are treated as if they were passive, i.e. the dosimetry service reads their indicated values and reports them to the evaluation organization.
In this document, the corrected indicated (corrected indication) value is the one given by the dosimetry systems as the final result of the evaluation algorithm (for example display of the software, printout) in units of dose equivalent (Sv).
Environmental dosemeters usually indicate the quantity H*(10) but they can, in addition or alternatively, indicate the quantity H'(3), H'(0,07), air kerma, Ka, or absorbed dose, D. All these dosemeters can also be treated according to this document. If Ka or D is indicated (in Gy) the dose values in this document stated in Sv shall then be interpreted as equivalent values in Gy.
- Standard26 pagesEnglish languagesale 10% offe-Library read for1 day
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.
- Standard36 pagesEnglish languagesale 10% offe-Library read for1 day
This document gives guidance on
a) confidentiality of personal information for the customer and the laboratory,
b) laboratory safety requirements,
c) calibration sources and calibration dose ranges useful for establishing the reference dose-response curves that contribute to the dose estimation from CBMN assay yields and the detection limit,
d) performance of blood collection, culturing, harvesting, and sample preparation for CBMN assay scoring,
e) scoring criteria,
f) conversion of micronucleus frequency in BNCs into an estimate of absorbed dose,
g) reporting of results,
h) quality assurance and quality control, and
i) informative annexes containing sample instructions for customers, sample questionnaire, a microscope scoring data sheet, and a sample report.
This document excludes methods for automated scoring of CBMN.
- Standard45 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the dosimetric and organizational criteria and the test procedures to be used for the periodic verification of the performance of dosimetry services supplying personal and/or area, i.e. workplace and/or environmental, dosemeters used for individual (personal) and/or area, i.e. workplace and/or environmental monitoring. NOTE The quality of a supplier of a dosimetry service depends on both the characteristics of the approved (type‑tested) dosimetry system and the training and experience of the staff, together with the calibration procedures and quality assurance programmes. The performance evaluation according to this document can be carried out by a dosimetry service to demonstrate the fulfilment of specified performance requirements. The irradiation qualities used in this document are representative for exposure situations that are expected or mimic workplace fields from the radiological activities being monitored using the dosemeters from the services. This document applies to personal and area dosemeters for the assessment of external photon radiation with a fluence-weighted mean energy between 8 keV and 10 MeV, beta radiation with a fluence-weighted mean energy between 60 keV and 1,2 MeV, and neutron radiation with a fluence-weighted mean energy between 25,3 meV, i.e. thermal neutrons with a Maxwellian energy distribution with kT = 25,3 meV, and 200 MeV. It covers all types of personal and area dosemeters needing laboratory processing (e.g. thermoluminescent, optically stimulated luminescence, radiophotoluminescent, track detectors or photographic-film dosemeters) and involving continuous measurements or measurements repeated regularly at fixed time intervals (e.g. several weeks, one month). Active direct reading as well as semi-passive or hybrid dosemeters, such as direct ion storage (DIS) or silicon photomultiplier (SiPM) dosemeters, for dose measurement, can also be treated according to this document. Then, they are treated as if they were passive, i.e. the dosimetry service reads their indicated values and reports them to the evaluation organization. In this document, the corrected indicated (corrected indication) value is the one given by the dosimetry systems as the final result of the evaluation algorithm (for example display of the software, printout) in units of dose equivalent (Sv). Environmental dosemeters usually indicate the quantity H*(10) but they can, in addition or alternatively, indicate the quantity H'(3), H'(0,07), air kerma, Ka, or absorbed dose, D. All these dosemeters can also be treated according to this document. If Ka or D is indicated (in Gy) the dose values in this document stated in Sv shall then be interpreted as equivalent values in Gy.
- Standard19 pagesEnglish languagesale 15% off
- Standard20 pagesFrench languagesale 15% off
This document gives guidance on
a) confidentiality of personal information for the customer and the laboratory,
b) laboratory safety requirements,
c) calibration sources and calibration dose ranges useful for establishing the reference dose-response curves that contribute to the dose estimation from CBMN assay yields and the detection limit,
d) performance of blood collection, culturing, harvesting, and sample preparation for CBMN assay scoring,
e) scoring criteria,
f) conversion of micronucleus frequency in BNCs into an estimate of absorbed dose,
g) reporting of results,
h) quality assurance and quality control, and
i) informative annexes containing sample instructions for customers, sample questionnaire, a microscope scoring data sheet, and a sample report.
This document excludes methods for automated scoring of CBMN.
- Standard45 pagesEnglish languagesale 10% offe-Library read for1 day
This document specifies the applicable requirements related to the design and the operation of confinement and ventilation systems for fusion facilities for tritium fuels and tritium fuel handling facilities specific for fusion applications for peaceful purposes using high tritium inventories, as well as for their specialized buildings such as hot cells, examination laboratories, emergency management centres, radioactive waste treatment and storage facilities. In most countries, a tritium quantity is declared as high for tritium inventories higher than a range of 10 g to 100 g. In the tritium fusion facilities in the scope of this document, the tritium inventory is deemed to be higher than this range for the whole site. This document applies especially to confinement and ventilation systems that ensure the safety function of nuclear facilities involved in nuclear fusion with the goal to protect the workers, the public and the environment from the dissemination of radioactive contamination originating from the operation of these installations, and in particular from airborne tritium contamination with adequate confinement systems. The types of confinement systems for other facilities are covered by ISO 26802 for fission nuclear reactors, by ISO 17873 for facilities other than fission nuclear reactors and by ISO 16647 for nuclear worksite and for nuclear installations under decommissioning. The facilities covered by these three standards, notably ISO 17873, include tritium as a radioactive material among the ones to be confined, but tritium is not their driver of the risks for workers and for members of the public. Nevertheless, the tritium quantities and risks from fusion facilities create specificities for a specific standard (e.g. in fusion facilities, tritium is the driver of routine and accident consequences). Therefore, the scope of this document does not cover the other facilities involved in tritium releases (ISO 17873, ISO 16647 and ISO 26802), even though these other facilities create tritium releases (e.g. non-reactor fission facilities, tritium laboratories, tritium removal facilities from fission plants, tritium defence facilities).
- Standard80 pagesEnglish languagesale 15% off
- Standard89 pagesFrench languagesale 15% off
This document gives guidance on a) confidentiality of personal information for the customer and the laboratory, b) laboratory safety requirements, c) calibration sources and calibration dose ranges useful for establishing the reference dose-response curves that contribute to the dose estimation from CBMN assay yields and the detection limit, d) performance of blood collection, culturing, harvesting, and sample preparation for CBMN assay scoring, e) scoring criteria, f) conversion of micronucleus frequency in BNCs into an estimate of absorbed dose, g) reporting of results, h) quality assurance and quality control, and i) informative annexes containing sample instructions for customers, sample questionnaire, a microscope scoring data sheet, and a sample report. This document excludes methods for automated scoring of CBMN.
- Standard35 pagesEnglish languagesale 15% off
- Standard38 pagesFrench languagesale 15% off
This document deals with the terminological data used in the standards regarding the standardization and promotion of good practices associated with the planning, design, construction, operation and decommissioning of installations, processes and technologies involving radioactive materials. The vocabulary of nuclear installations, processes and technologies includes fuel cycle, ex-reactor nuclear criticality safety, analytical methodologies, transport of radioactive materials, materials characterization, radioactive waste management and decommissioning. NOTE See Annex A for the methodology used to develop the vocabulary.
- Standard24 pagesEnglish languagesale 15% off
This document 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).
- Standard32 pagesEnglish languagesale 10% offe-Library read for1 day
This document 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.
- Standard39 pagesEnglish languagesale 10% offe-Library read for1 day
IEC 61526:2024 applies to personal dosemeters with the following characteristics:
a) They are worn on the trunk, close to the eye, or on the extremities.
b) They measure the personal dose equivalents Hp(10), Hp(3), and Hp(0,07), from external X and gamma, neutron (not for Hp(3)), and beta radiations, and may measure the respective personal dose equivalent rates for the same radiations (for alarming purposes).
c) They have a digital indication. This indication may or may not be attached.
d) They have alarm functions for the personal dose equivalents or personal dose equivalent rates except for hybrid dosemeters. For hybrid dosemeters an alarm function for the personal dose equivalents shall be implemented in the associated readout system.
This document specifies requirements for the dosemeter and, if supplied, for its associated readout system.
This document specifies, for the dosemeters described above, general characteristics, general test procedures, radiation characteristics as well as electrical, mechanical, safety and environmental characteristics.
This edition includes the following significant technical changes with respect to the previous edition:
a) Modification of the title;
b) Inclusion of the measurement quantity for the dose in the lens of the eye, Hp(3);
c) Inclusion of measurement quantity for dose in the skin and extremities, Hp(0,07);
d) Inclusion of dosemeters between active and passive: "hybrid dosemeters";
e) Inclusion of software requirements;
f) Harmonization of requirements for linearity to IEC 62387;
g) Revised neutron energy response requirements.
- Standard166 pagesEnglish and French languagesale 15% off
This document 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. It is not applicable to the user passes quickly through the monitor. It is also not applicable to any peripheral equipment which may be associated with a particular type of equipment such as small article monitors. Probes (friskers) for measuring clothes or body by the person under monitoring or someone else are included in this document.
- Standard73 pagesEnglish languagesale 10% offe-Library read for1 day
This document 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.
- Standard39 pagesEnglish languagesale 10% offe-Library read for1 day