This document specifies methods for the measurement of the absorbed-dose rate in a tissue-equivalent slab phantom in the ISO 6980 reference beta-particle radiation fields. The energy range of the beta-particle-emitting isotopes covered by these reference radiations is 0,22 MeV to 3,6 MeV maximum beta energy corresponding to 0,07 MeV to 1,2 MeV mean beta energy. Radiation energies outside this range are beyond the scope of this document. While measurements in a reference geometry (depth of 0,07 mm or 3 mm at perpendicular incidence in a tissue‑equivalent slab phantom) with an extrapolation chamber used as primary standard are dealt with in detail, the use of other measurement systems and measurements in other geometries are also described, although in less detail. However, as noted in ICRU 56, the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is intended for those organizations wishing to establish primary dosimetry capabilities for beta particles and serves as a guide to the performance of dosimetry with an extrapolation chamber used as primary standard for beta‑particle dosimetry in other fields. Guidance is also provided on the statement of measurement uncertainties.

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This document describes procedures for calibrating and determining the response of dosemeters and dose-rate meters in terms of the operational quantities for radiation protection purposes defined by the International Commission on Radiation Units and Measurements (ICRU). However, as noted in ICRU 56, the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is a guide for those who calibrate protection-level dosemeters and dose-rate meters with beta-reference radiation and determine their response as a function of beta-particle energy and angle of incidence. Such measurements can represent part of a type test during the course of which the effect of other influence quantities on the response is examined. This document does not cover the in-situ calibration of fixed, installed area dosemeters. The term “dosemeter” is used as a generic term denoting any dose or dose-rate meter for individual or area monitoring. In addition to the description of calibration procedures, this document includes recommendations for appropriate phantoms and the way to determine appropriate conversion coefficients. Guidance is provided on the statement of measurement uncertainties and the preparation of calibration records and certificates.

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This document provides information and guidelines on the decommissioning of a medical cyclotron facility, with a focus on activated or contaminated parts. Useful information and guidelines are given on decommissioning strategy and plan, safety assessment, and various decommissioning activities. This document also provides the guideline on the estimation of activation level using Monte Carlo simulation and the methodology for the measurement of activated radionuclides in the main structure, system components, and shielding walls, ceilings and floors during operation and decommissioning. Financial provisions and radioactive waste management aspects are also included. This document can be used by organizations responsible for operation and decommissioning of a medical cyclotron facility. In addition, it is expected that organizations that design a medical cyclotron or manage radioactive waste generated by cyclotron can utilize or refer to this document in whole or in part.

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This document specifies the requirements for reference beta radiation fields produced by radioactive sources to be used for the calibration of personal and area dosemeters and dose-rate meters to be used for the determination of the quantities Hp(0,07), H'(0,07;Ω), Hp(3) and H'(3;Ω), and for the determination of their response as a function of beta particle energy and angle of incidence. The basic quantity in beta dosimetry is the absorbed-dose rate in a tissue-equivalent slab phantom. This document gives the characteristics of radionuclides that have been used to produce reference beta radiation fields, gives examples of suitable source constructions and describes methods for the measurement of the residual maximum beta particle energy and the dose equivalent rate at a depth of 0,07 mm in the International Commission on Radiation Units and Measurements (ICRU) sphere. The energy range involved lies between 0,22 MeV and 3,6 MeV maximum beta energy corresponding to 0,07 MeV to 1,2 MeV mean beta energy and the dose equivalent rates are in the range from about 10 µSv·h-1 to at least 10 Sv·h-1.. In addition, for some sources, variations of the dose equivalent rate as a function of the angle of incidence are given. However, as noted in ICRU 56[5], the ambient dose equivalent, H*(10), used for area monitoring, and the personal dose equivalent, Hp(10), as used for individual monitoring, of strongly penetrating radiation, are not appropriate quantities for any beta radiation, even that which penetrates 10 mm of tissue (Emax > 2 MeV).
This document is applicable to two series of reference beta radiation fields, from which the radiation necessary for determining the characteristics (calibration and energy and angular dependence of response) of an instrument can be selected.
Series 1 reference radiation fields are produced by radioactive sources used with beam-flattening filters designed to give uniform dose equivalent rates over a large area at a specified distance. The proposed sources of 106Ru/106Rh, 90Sr/90Y, 85Kr, 204Tl and 147Pm produce maximum dose equivalent rates of approximately 200 mSv·h–1.
Series 2 reference radiation fields are produced without the use of beam-flattening filters, which allows large area planar sources and a range of source-to-calibration plane distances to be used. Close to the sources, only relatively small areas of uniform dose rate are produced, but this series has the advantage of extending the energy and dose rate ranges beyond those of series 1. The series also include radiation fields using polymethylmethacrylate (PMMA) absorbers to reduce the maximum beta particle energy. The radionuclides used are those of series 1; these sources produce dose equivalent rates of up to 10 Sv·h–1.

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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 complements the existing requirements of ISO/IEC 17021-1 for bodies providing audit and certification of quality management systems against ISO 19443.
NOTE          This document can be used as a criteria document for accreditation, peer assessment or other audit processes.

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This document complements the existing requirements of ISO/IEC 17021-1 for bodies providing audit and certification of quality management systems against ISO 19443.
NOTE          This document can be used as a criteria document for accreditation, peer assessment or other audit processes.

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This document complements the existing requirements of ISO/IEC 17021-1 for bodies providing audit and certification of quality management systems against ISO 19443. NOTE This document can be used as a criteria document for accreditation, peer assessment or other audit processes.

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This document is applicable to housed scintillators for registration and spectrometry of alpha-, beta-, gamma-, X-ray and neutron radiation. Their basic parameters such as a light output and intrinsic resolution are established. The document  does not apply to gas or liquid scintillators and scintillators for counting or
current measurement.

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This document is applicable to housed scintillators for registration and spectrometry of alpha-, beta-, gamma-, X-ray and neutron radiation. Their basic parameters such as a light output and intrinsic resolution are established. The document does not apply to gas or liquid scintillators and scintillators for counting or current measurement.

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This document provides guidance on the implementation of the ISO 19443 requirements, with examples of possible steps an organization can take to meet the requirements.
It does not add to, subtract from, or in any way modify those requirements.
This document does not prescribe mandatory approaches to implementation, or provide any preferred method of interpretation.

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This document provides guidance on the implementation of the ISO 19443 requirements, with examples of possible steps an organization can take to meet the requirements.
It does not add to, subtract from, or in any way modify those requirements.
This document does not prescribe mandatory approaches to implementation, or provide any preferred method of interpretation.

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This International Standard specifies requirements for a quality management system when an organization:
a)    needs to demonstrate its ability to consistently provide products and services that meet customer and applicable statutory and regulatory requirements, and
b)    aims to enhance customer satisfaction through the effective application of the system, including processes for improvement of the system and the assurance of conformity to customer and applicable statutory and regulatory requirements.
All the requirements of this International Standard are generic and are intended to be applicable to any organization, regardless of its type or size, or the products and services it provides.
NOTE 1    In this International Standard, the terms "product" or "service" only apply to products and services intended for, or required by, a customer.
NOTE 2    Statutory and regulatory requirements can be expressed as legal requirements.
This International Standard applies to organizations supplying ITNS products or services.
Application of this standard to organizations performing activities on a licensed nuclear site is subject to prior agreement by the Licensee.
Requirements specified in this International Standard are complementary (not alternative) to customer and applicable statutory and regulatory requirements.

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This International Standard specifies requirements for a quality management system when an organization:
a)    needs to demonstrate its ability to consistently provide products and services that meet customer and applicable statutory and regulatory requirements, and
b)    aims to enhance customer satisfaction through the effective application of the system, including processes for improvement of the system and the assurance of conformity to customer and applicable statutory and regulatory requirements.
All the requirements of this International Standard are generic and are intended to be applicable to any organization, regardless of its type or size, or the products and services it provides.
NOTE 1    In this International Standard, the terms "product" or "service" only apply to products and services intended for, or required by, a customer.
NOTE 2    Statutory and regulatory requirements can be expressed as legal requirements.
This International Standard applies to organizations supplying ITNS products or services.
Application of this standard to organizations performing activities on a licensed nuclear site is subject to prior agreement by the Licensee.
Requirements specified in this International Standard are complementary (not alternative) to customer and applicable statutory and regulatory requirements.

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This document gives the rules of naming, technical requirements, test methods, inspection, marking, packaging, transportation, storage and accompanying documents for electron linear accelerator equipment for Non-Destructive Testing (NDT). This document applies to NDT electron linear accelerator equipment in the X-ray energy range of 1 MeV to 15 MeV, including the accelerator equipment for radiographic film,computed radiography with imaging plates, real-time imaging, digital detector array and industrial computerized tomography.

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IEC 63175:2021 is applicable to hydrogen ion H- acceleration proton cyclotrons with one or more fixed energies within the range of 10 MeV to less than 30 MeV and a beam intensity equal to or greater than 300 μA. This document specifies the performance and safety requirements, structure, technical requirements, test methods, identification, packing, transportation, storage and accompanying documents for such cyclotrons. This document is intended for manufacturers of high intensity proton cyclotron within the energy range of 10 MeV to less than 30 MeV, and responsible organizations where such cyclotrons are installed.

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IEC 62976:2017 gives the rules of naming, technical requirements, test methods, inspection, marking, packaging, transportation, storage and accompanying documents for electron linear accelerator equipment for Non-Destructive Testing (NDT). This document applies to NDT electron linear accelerator equipment in the X-ray energy range of 1 MeV to 15 MeV, including the accelerator equipment for radiographic film, computed radiography with imaging plates, real-time imaging, digital detector array and industrial computerized tomography.

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  • Standard
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IEC 63148:2021 specifies the requirements of tracking systems for radioactive materials. Such systems identify and locate the position of the radioactive materials transported using global navigation satellite systems (GNSS) and radio frequency identification (RFID).
The system provides a set of safety controls of the radioactive material, by which the transporter can improve safety during transportation. This document may also be used as supplementary guidance to the regulatory body.

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This document specifies the format of binary list-mode data at the output of digital data acquisition devices used for the detection and measurement of radiation. Such data acquisition devices may employ digital signal processors (DSP) and field-programmable gate arrays (FPGA) in combination with memory and a communication interface with a computer.

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This document specifies the format of binary list-mode data at the output of digital data acquisition devices used for the detection and measurement of radiation. Such data acquisition devices may employ digital signal processors (DSP) and field-programmable gate arrays (FPGA) in combination with memory and a communication interface with a computer.

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IEC 62372:2021 is applicable to housed scintillators for registration and spectrometry of alpha-, beta-, gamma-, X-ray and neutron radiation. This document specifies the requirements for the testing equipment and test methods of the basic parameters, of housed scintillators, such as:
- the direct method is applicable to measure the light output of housed scintillators based on scintillation material. The housed scintillators certified by this method can be used as working standard of housed scintillators (hereinafter: working standard) when performing measurements by a relative method of comparison.
- the relative method of comparison with the working standard is applicable to housed scintillators based on the same scintillation material as the working standard.
This second edition cancels and replaces the first edition published in 2006. This edition includes the following significant technical changes with respect to the previous edition:
- Title has been modified.
- To review the existing requirements and to update the terminology, definitions and normative references.

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  • Standard
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IEC 63048:2020 defines the general requirements for Mobile Remotely Controlled Systems (MRCSs) for nuclear and radiological applications such as integrity inspections, repair of components, handling of radioactive materials, and monitoring of physical conditions and radiation dose intensity in specific areas.
This document applies to MRCSs that are used to support nuclear and radiological facilities. These general requirements encompass high-level performance requirements regarding sensors, monitoring devices, control devices, interfacing mechanisms, simulation methods, and verification methods thereof in a normal environment or extreme environmental conditions, such as high radiation, high temperature, and high humidity environments.

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This document provides guidance on the implementation of the ISO 19443 requirements, with examples of possible steps an organization can take to meet the requirements. It does not add to, subtract from, or in any way modify those requirements. This document does not prescribe mandatory approaches to implementation, or provide any preferred method of interpretation.

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  • Technical report
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  • Technical report
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This document contains the terms, definitions, notes to entry and examples corresponding to the basic concepts of the nuclear energy, nuclear technologies, and radiological protection subject fields. It provides the minimum essential information for each cross-cutting concept represented by a single term. NOTE A full understanding of concepts goes with a background knowledge of nuclear energy, nuclear technologies, and radiological protection. It is intended to facilitate communication and promote common understanding.

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This document gives the rules of naming, technical requirements, test methods, inspection, marking, packaging, transportation, storage and accompanying documents for electron linear accelerator equipment for Non-Destructive Testing (NDT).
This document applies to NDT electron linear accelerator equipment in the X-ray energy range of 1 MeV to 15 MeV, including the accelerator equipment for radiographic film,computed radiography with imaging plates, real-time imaging, digital detector array and industrial computerized tomography.

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This International Standard specifies requirements for a quality management system when an organization: a) needs to demonstrate its ability to consistently provide products and services that meet customer and applicable statutory and regulatory requirements, and b) aims to enhance customer satisfaction through the effective application of the system, including processes for improvement of the system and the assurance of conformity to customer and applicable statutory and regulatory requirements. All the requirements of this International Standard are generic and are intended to be applicable to any organization, regardless of its type or size, or the products and services it provides. NOTE 1 In this International Standard, the terms "product" or "service" only apply to products and services intended for, or required by, a customer. NOTE 2 Statutory and regulatory requirements can be expressed as legal requirements. This International Standard applies to organizations supplying ITNS products or services. Application of this standard to organizations performing activities on a licensed nuclear site is subject to prior agreement by the Licensee. Requirements specified in this International Standard are complementary (not alternative) to customer and applicable statutory and regulatory requirements.

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IEC 60412:2014 gives guidelines for scintillation detectors and scintillators nomenclature (identification) and standard dimensions of scintillators. This International Standard is applicable to all types of solid organic and inorganic scintillators used in detectors for scintillation counting and spectrometry. The object of this standard is to define a standardized nomenclature for scintillation detectors in which most of the properties can be found. The object of this standard is also to standardize the dimensions of bare scintillators in order to facilitate interchangeability of non-encapsulated scintillators and to facilitate intercomparisons of measurements with encapsulated scintillators. The main technical changes with regard to the previous edition are as follows:
- nomenclature of scintillation detectors was expanded by phoswich detector and single-line multi-channel detector;
- some missing positions in the nomenclature of the previous edition were filled out.

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IEC 60050-395:2014 gives the general terminology used in nuclear concepts, instruments, systems, equipment and detectors. This terminology is consistent with the terminology published in the other specialized parts of the IEV.
It has the status of a horizontal standard in accordance with IEC Guide 108.

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IEC 62598:2011 applies to the manufacture and installation of electrical measuring systems and instruments utilizing radioactive sources (radiometric gauges, hereinafter called gauges). It also applies to source housings intended for use in the aforementioned measuring systems. This standard applies to equipment, which is not related to power production or to the fuel cycle. It specifies constructional requirements for the design of instruments utilizing radioactive sources in regard of radiation protection. This standards cancels and replaces IEC 60405.

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IEC 61435:2013(E) is applicable to high-purity germanium crystals used for radiation detectors for gamma-rays and X-rays. Such germanium is monocrystalline and has a net concentration of fewer than 1011 electrically active impurity centers per cm3. This International Standard specifies terminology and test methods for measurements of basic characteristics of high-purity germanium crystals. Test methods for completed assembled germanium detectors are given in IEC 60973 and IEC 60759. The main technical changes with regard to the previous edition are as follows:
- review the existing requirements;
- update the terminology and definitions.

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IEC 62495:2011(E) is applicable to the radiological safety of portable handheld X-ray fluorescence (XRF) analysis equipment utilizing a miniature X-ray tube as the source of ionizing radiation for industrial applications. Establishes performance specifications for general radiation, electrical, safety and environmental characteristics of the design and operation, and test methods in relation to radiological safety for portable XRF analysis equipment utilizing a miniature X-ray tube. The proposed performance specifications are aimed at minimizing and avoiding the health risk associated with the use of these devices.

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IEC 62598:2011 applies to the manufacture and installation of electrical measuring systems and instruments utilizing radioactive sources (radiometric gauges, hereinafter called gauges). It also applies to source housings intended for use in the aforementioned measuring systems. This standard applies to equipment, which is not related to power production or to the fuel cycle. It specifies constructional requirements for the design of instruments utilizing radioactive sources in regard of radiation protection. This standards cancels and replaces IEC 60405.

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  • Standard
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IEC 60462:2010(E) establishes test procedures for photomultiplier tubes (PMT) for scintillation and Cherenkov detectors. The tests described are supplementary to those described in IEC 60306-4. The main technical changes of this new edition with regard to the previous one are as follows:
- the requirements have been revised and the terminology,
- definitions and normative references have been brought up-to-date.

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    23 pages
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Specifies methods of calibration and routine tests of scintillation detector systems for the measurement of gamma-ray energies and emission rates of radionuclides and the assay of radioactivity. Is applicable to scintillation detector systems based on inorganic scintillators for photon measurements. This second edition reflects an expansion of detector types considered.

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    37 pages
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Gives guidelines for scintillation detectors nomenclature (identification) and standard dimensions of scintillators. Is applicable to all types of solid organic and inorganic scintillators used in detectors for scintillation counting and spectrometry. The purpose is to facilitate interchangeability of non-encapsulated scintillators and to facilitate comparisons of measurements with encapsulated scintillators. The main change with respect to the previous edition is the addition of the nomenclature.

  • Standard
    20 pages
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Is applicable to housed scintillators for registration and spectrometry of alpha-, beta-, gamma-, X-ray and neutron radiation. Establishes basic parameters such as a light output and intrinsic resolution and specifies the requirements for the equipment and the methods of defining the basic parameters.

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    35 pages
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Recommends a limited family of preferred standard coaxial connectors for nuclear laboratory instruments. Applies to coaxial connectors for electrical instruments used in nuclear laboratories.

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    11 pages
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Establishes standard methods for calibration and use of alpha/beta gas proportional counters, including measurement of their characteristics. Applies to alpha/beta gas proportional counting systems used for the determination of the alpha-ray or beta-ray emission rates of radionuclides in sample counting.

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    67 pages
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Establishes standard test procedures for photodiodes used in scintillation detectors and defines the parameters which shall be provided by the supplier for each type of photodiode.

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    35 pages
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It has the status of a horizontal standard in accordance with IEC Guide 108.

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