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.

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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.

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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.

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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).

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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.

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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.

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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.
This document establishes the operational and testing requirements associated with radiation
measurements and the expected electrical, mechanical, and environmental conditions while in
use.
This document does not apply to ambient or personal dose equivalent rate meters which are
covered in IEC 60846-1 or IEC 61526, respectively.

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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).

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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.

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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 can 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. The probes
(friskers) are always connected to 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 document is applicable to:
– installed personnel monitor (all clauses applicable);
– transportable personnel monitor (all clauses applicable);
– monitor for monitoring the hands (see the following clauses and subclauses: 2, 3, 4, 5, 6,
7.1.3, 7.2, 7.3.4, 7.4.2.2 b), 7.4.3, 7.4.4.1, 7.4.4.2, 7.4.4.3 b), 7.5, 7.6, 7.7, 8, 9, 10, 11, 12,
13 and 14);
– monitor for monitoring the feet (see the following clauses and subclauses: 2, 3, 4, 5, 6,
7.1.4, 7.2, 7.3.5, 7.4.2.2 c), 7.4.3, 7.4.4.1, 7.4.4.2, 7.4.4.3 c), 7.5, 7.6, 7.7, 8, 9, 10, 11, 12,
13 and 14); and
– monitor for monitoring the hands and feet (including probe (frisker) for whole body
measurement) (see the following clauses and subclauses: 2, 3, 4, 5, 6, 7.1.3, 7.1.4, 7.1.5,
7.2, 7.3.4, 7.3.5, 7.3.6, 7.4.2.2 b), 7.4.2.2 c), 7.4.2.2 d), 7.4.3, 7.4.4.1, 7.4.4.2, 7.4.4.3 b),
7.4.4.3 c), 7.4.4.3 d),7.5, 7.6, 7.7, 8, 9, 10, 11, 12, 13 and 14).
The object of this document is to define mechanical and operational characteristics, minimum
performance characteristics and general test procedures for personnel monitors.

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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).

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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.

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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.

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This document presents general principles for preparedness to conduct individual contamination screening, triage, monitoring and assessing radiation doses received by people exposed during and/or in the aftermath of a nuclear or major radiological incident. The document mainly focuses on the early response phase, which requires rapid actions to be undertaken for achieving the goals in support of, and according to, national or international guidelines on emergency response. It addresses general requirements for — members of the public, this includes adults, vulnerable populations (such as children and pregnant women) and people with special needs (such as the elderly and disabled), and — emergency workers. This document provides general procedures for screening, triage and monitoring these two categories of people. It deals with individual monitoring for potential external contamination, internal and external exposures and dose assessment. It also gives principles for organizing and managing a population screening centre and for registering and reporting the results of individual monitoring. This document is applicable to most exposure situations following a nuclear or major radiological incident affecting a large number of people, including: — significant release of radioactive materials (e.g. from a facility or nuclear power plant, during transportation); — radiological dispersal device (RDD); — improvised nuclear device (IND); — nuclear weapon. Radiological incidents for which there is no release of radioactive material in the environment but only external exposures (e.g. linked to a Radiation Exposure Device (RED)) are outside the scope of this document[1]. However, some information given by this document may be of interest for this type of event. The aim of the document is to ensure that the appropriate parties are prepared in advance. This document advises how to obtain and collect data quickly and accurately in order to inform decision makers. It does not specify the parties or individuals who are responsible for undertaking the actions. This document is intended to give guidance to those in charge of monitoring and assessing doses received by populations in emergency exposure situations involving a large number of people potentially subject to internal/external contamination (and subsequent radiation doses). It can also serve as guidance to regulatory bodies. [1] Incidents resulting from RED exposure are excluded from consideration in this document because they do not result in contamination that would be detected by a portal monitor or handheld device. Identification of victims with only potential external exposure are determined by means such as evaluation of clinical signs and symptoms, biodosimetry, EPR, etc.

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This product standard applies to wireless communication devices used in close proximity to the human ear (e.g. mobile phones, wireless headsets). The applicable frequency range is from 300 MHz to 6 GHz.
The objective of this standard is to demonstrate the compliance of such devices with the basic restrictions and exposure limit values related to human exposure to radio frequency electromagnetic fields.
For devices used next to the body or in front of the face the applicable product standard is EN 50566:2017.
For low power devices the applicable product standard is EN 50663:2017.

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The objective of this document is to promote the harmonization of data and information reporting formats in order to provide the basis for the evaluation of occupational exposure with a view to allow for benchmarking capacity at the user level, technical review level, country level and global level (such as UNSCEAR) database or register on occupational exposure. Activity sectors and occupations (where employees are classified as occupationally exposed workers) that is included in this database or register as well as dose types and different values of interest concerning occupational exposure are described as follows. A typical national dose register (NDR): — contains personal, employment, and dosimetric data of occupational employment and wage statistics (OEWs) in the country. — assists national authorities in controlling and safekeeping of the occupational doses and to allow statistical evaluations (e.g., dose trends to answer requests from regulators and others). — assists in regulatory control by notifying regulatory authorities of overexposures within their jurisdiction and the licensee in their respective facility. — contributes to health research and to the scientific knowledge on risks from occupational exposure to ionizing radiation. — provides dose histories to individual workers and organizations for work planning and for compensation and litigation cases. All information provided by the NDR, including dose histories, may be subject to confidentiality requirements. This document is aimed at national dose registries but may be also applicable to dosimetry services that provide data to national dose registries. NOTE Such a database or register on occupational radiation dose for different sectors will, among other reasons, allow to prepare the data necessary for more global surveys, such as those undertaken by the UNSCEAR and other databases such as IAEA’s Information System on Occupational Exposure in Medicine, Industry and Research (ISEMIR), Information System on Occupational Exposure (ISOE) and the European Platform for Occupational Radiation Exposure (ESOREX‑Platform). Presently, as the formats are different, the international description of national statistics is often incomplete or inaccurate, and in the end, the comparison of data is not established yet in many countries. This standard defines a common and easily shared format to collect reliable, traceable and directly comparable data on individual and collective exposure in activity sectors and occupations as defined in a common way. This document addresses: a) a common list of activity sectors and occupations, and b) a common and easily shared format about dose types and different values of interest concerning occupational exposure in order to collect consistent and directly comparable data on individual and collective exposure.

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This document specifies a method for the simultaneous measurement of 3H and 14C in water samples by liquid scintillation counting of a source obtained by mixing the water sample with a hydrophilic scintillation cocktail. The method presented in this document is considered a screening method because of the potential presence of interfering radionuclides in the test sample. However, if the sample is known to be free of interfering radionuclides then 3H and 14C can be measured quantitatively. The method can be used for any type of environmental study or monitoring. This method is applicable to test samples of supply/drinking water, rainwater, surface and ground water, marine water, as well as cooling water, industrial water, domestic, and industrial wastewater having an activity concentration ranging from 5 Bq∙l-1 to 106 Bq∙l-1 (upper limit of the liquid scintillation counters for direct counting). For higher activity concentrations, the sample can be diluted to obtain a test sample within this range.

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This product standard applies to wireless communication devices used at distances up to and including 200 mm from the human body, i.e. when held in the hand or in front of the face, mounted on the body, combined with other transmitting or non-transmitting devices or accessories (e.g. belt-clip, camera or Bluetooth add-on), or integrated into garments. The applicable frequency range is from 30 MHz to 6 GHz.
The objective of this standard is to demonstrate the compliance of such devices with the basic restrictions and exposure limit values related to human exposure to radio frequency electromagnetic fields.
For devices used next to the ear the applicable product standard is EN 50360:2017 [1].
For low power devices the applicable product standard is EN 50663:2017 [2].

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This European Standard deals with the safety of electric washing machines for household and similar use, that are intended for washing clothes and textiles, their rated voltage being not more than 250 V for single-phase appliances and 480 V for other appliances.

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This European Standard deals with the safety of electric washing machines for household and similar use, that are intended for washing clothes and textiles, their rated voltage being not more than 250 V for single-phase appliances and 480 V for other appliances.

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This European Standard deals with the safety of electric washing machines for household and similar use, that are intended for washing clothes and textiles, their rated voltage being not more than 250 V for single-phase appliances and 480 V for other appliances.

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ISO 13164-4:2015 describes a test method for the determination of radon-222 (222Rn) activity concentration in non-saline waters by extraction and liquid scintillation counting.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, are at least above 0,5 Bq l−1 for a 10 ml test sample and a measuring time of 1 h.
This test method can be used successfully with drinking water samples and it is the responsibility of the laboratory to ensure the validity of this test method for water samples of untested matrices.
Annex A gives indication on the necessary counting conditions to meet the required detection limits for drinking water monitoring.

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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).

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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).

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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).

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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.

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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.

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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.

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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.

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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

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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.

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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).

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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.

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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.

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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).

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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.

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