| Name |
Description |
Abstract |
Status |
Publication date |
Edition |
Number of pages |
Technical committee |
ICS |
| ISO 19238:2014 |
Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics |
ISO 19238:2014 provides criteria for quality assurance and quality control, evaluation of the performance, and the accreditation of biological dosimetry by cytogenetic service laboratories.
ISO 19238:2014 addresses
a) the confidentiality of personal information, for the customer and the service laboratory,
b) the laboratory safety requirements,
c) the calibration sources and calibration dose ranges useful for establishing the reference dose-effect curves that contribute to the dose estimation from chromosome aberration frequency and the minimum resolvable doses,
d) the scoring procedure for unstable chromosome aberrations used for biological dosimetry,
e) the criteria for converting a measured aberration frequency into an estimate of absorbed dose,
f) the reporting of results,
g) the quality assurance and quality control,
h) informative annexes containing sample instructions for customer, sample questionnaire, sample of report, fitting of the low dose-response curve by the method of maximum likelihood and calculating the error of dose estimate, odds ratio method for cases of suspected exposure to a low dose, and sample data sheet for recording aberrations.
|
Published |
2014-02 |
Edition : 2 |
Number of pages : 29 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 156:1982 |
Metallic materials — Hardness test — Verification of Brinell hardness testing machines |
|
Withdrawn |
1982-09 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 19461-1:2018 |
Radiological protection — Measurement for the clearance of waste contaminated with radioisotopes for medical application — Part 1: Measurement of radioactivity |
This document establishes a method for radioactivity measurement and determination of the storage periods of the radioactive wastes produced as a result of the medical application of radioisotopes based on counting measurements using a detector and decay correction of the initial activity concentration of the radioisotopes contained in the waste stream.
It provides a set of controls and measurements for the self-clearance of the radioactive wastes by which the medical facility can be assured of meeting the clearance level.
This document can also be used by testing laboratories or radioactive waste disposal operators.
This document can also be useful for the guidance of the regulatory body.
NOTE Due to the nature of the tests outlined, this document cannot be applied to pure beta emitting nuclides nor to alpha emitting nuclides with low energy gamma rays.
|
Published |
2018-07 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 19461-2:2022 |
Radiological protection — Measurement for the clearance of waste contaminated with radioisotopes for medical application — Part 2: Management of solid radioactive waste in nuclear medicine facilities |
This document addresses aspects of management of solid biomedical radioactive waste from its generation in nuclear medicine facilities to final clearance and disposal, as well as the manner to establish an effective program for biomedical radioactive waste management.
Liquid and gaseous wastes are excluded from the scope of the document, but solid waste includes spent and surplus solutions of radionuclides contained in vials, tubes or syringes. Therefore, this document should be useful for any nuclear medicine facilities dealing with in vivo medical applications of radionuclides and consequently with the waste associated with such applications.
This document provides a list of the main radionuclides used in nuclear medicine facilities and their main physical characteristics, as well as the guidance to write a radioactive waste management program for their sorting, collection, packaging and labelling, radioactivity surveys and decay storage, clearance levels, and transportation, if necessary, until their ultimate disposal or discharge. This document may also be useful as guidance for regulatory bodies.
|
Published |
2022-06 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 20031:2020 |
Radiological protection — Monitoring and dosimetry for internal exposures due to wound contamination with radionuclides |
This document specifies the requirements for personal contamination monitoring and dose assessment following wounds involving radioactive materials. It includes requirements for the direct monitoring at the wound site, monitoring of uptake of radionuclides into the body and assessment of local and systemic doses following the wound event.
It does not address:
— details of monitoring and assessment methods for specific radionuclides;
— monitoring and dose assessment for materials in contact with intact skin or pre-existing wounds, including hot particles;
— therapeutic protocols. However, the responsible entity needs to address the requirements for decontamination and decorporation treatments if appropriate.
|
Published |
2020-02 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
|
| ISO 20042:2019 |
Measurement of radioactivity — Gamma-ray emitting radionuclides — Generic test method using gamma-ray spectrometry |
This document describes the methods for determining the activity in becquerel (Bq) of gamma‑ray emitting radionuclides in test samples by gamma-ray spectrometry. The measurements are carried out in a testing laboratory following proper sample preparation. The test samples can be solid, liquid or gaseous. Applications include:
— routine surveillance of radioactivity released from nuclear installations or from sites discharging enhanced levels of naturally occurring radioactive materials;
— contributing to determining the evolution of radioactivity in the environment;
— investigating accident and incident situations, in order to plan remedial actions and monitor their effectiveness;
— assessment of potentially contaminated waste materials from nuclear decommissioning activities;
— surveillance of radioactive contamination in media such as soils, foodstuffs, potable water, groundwaters, seawater or sewage sludge;
— measurements for estimating the intake (inhalation, ingestion or injection) of activity of gamma-ray emitting radionuclides in the body.
It is assumed that the user of this document has been given information on the composition of the test sample or the site. In some cases, the radionuclides for analysis have also been specified if characteristic limits are needed. It is also assumed that the test sample has been homogenised and is representative of the material under test.
General guidance is included for preparing the samples for measurement. However, some types of sample are to be prepared following the requirements of specific standards referred to in this document. The generic recommendations can also be useful for the measurement of gamma-ray emitters in situ.
This document includes generic advice on equipment selection (see Annex A), detectors (more detailed information is included in Annex D), and commissioning of instrumentation and method validation. Annex F summarises the influence of different measurement parameters on results for a typical gamma-ray spectrometry system. Quality control and routine maintenance are also covered, but electrical testing of the detector and pulse processing electronics is excluded. It is assumed that any data collection and analysis software used has been written and tested in accordance with relevant software standards such as ISO/IEC/IEEE 12207.
Calibration using reference sources and/or numerical methods is covered, including verification of the results. It also covers the procedure to estimate the activity content of the sample (Bq) from the spectrum.
The principles set out in this document are applicable to measurements by gamma-ray spectrometry in testing laboratories and in situ. However, the detailed requirements for in situ measurement are given in ISO 18589-7 and are outside the scope of this document.
This document covers, but is not restricted to, gamma-ray emitters which emit photons in the energy range of 5 keV to 3 000 keV. However, most of the measurements fall into the range 40 keV to 2 000 keV. The activity (Bq) ranges from the low levels (sub-Bq) found in environmental samples to activities found in accident conditions and high level radioactive wastes.
|
Published |
2019-06 |
Edition : 1 |
Number of pages : 50 |
Technical Committee |
13.280
Radiation protection
|
| ISO 20043-1:2021 |
Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 1: Planned and existing exposure situation |
These international guidelines are based on the assumption that monitoring of environmental components (atmosphere, water, soil and biota) as well as food quality ensure the protection of human health[2][4][5][6][7][8]. The guidelines constitute a basis for the setting of national regulations and standards, 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, biological components) and food;
— guidance on the environmental characterization needed for the prospective and/or retrospective dose assessment methods of public exposure;
— 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 for 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.
Generic mathematical models used for the assessment of radiological human exposure are presented to identify the parameters to monitor, in order to select, from the set of measurement results, the "best estimates" of these parameter values. More complex models are often used that require the knowledge of supplementary parameters.
The reference and limit values are not included in this document.
|
Published |
2021-01 |
Edition : 1 |
Number of pages : 30 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO/FDIS 20043-2 |
Measurement of radioactivity in the environment — Guidelines for effective dose assessment using environmental monitoring data — Part 2: Emergency exposure situation |
|
Under development |
|
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 2533:1975/Add 1:1985 |
Standard Atmosphere — Addendum 1: Hypsometrical tables |
|
Published |
1985-02 |
Edition : 1 |
Number of pages : 76 |
Technical Committee |
07.060
Geology. Meteorology. Hydrology
;
17.020
Metrology and measurement in general
;
19.020
Test conditions and procedures in general
;
49.020
Aircraft and space vehicles in general
|
| ISO 20046:2019 |
Radiological protection — Performance criteria for laboratories using Fluorescence In Situ Hybridization (FISH) translocation assay for assessment of exposure to ionizing radiation |
The purpose of this document is to provide criteria for quality assurance (QA), quality control (QC) and evaluation of the performance of biological dosimetry by cytogenetic service laboratories.
This document addresses:
a) the responsibilities of both the customer and the laboratory;
b) the confidentiality of personal information, for the customer and the laboratory;
c) the laboratory safety requirements;
d) sample processing; culturing, staining and scoring, including the criteria for scoring for translocation analysis by FISH;
e) the calibration sources and calibration dose ranges useful for establishing the reference dose‑response curves that contribute to the dose estimation from chromosome aberration frequency and the detection limit;
f) the scoring procedure for translocations stained by FISH used for evaluation of exposure;
g) the criteria for converting a measured aberration frequency into an estimate of absorbed dose (also appears as "dose");
h) the reporting of results;
i) the QA and QC;
j) Annexes A to F containing sample instructions for the customer, sample questionnaire, sample datasheet for recording aberrations, sample of report and fitting of the low dose-response curve by the method of maximum likelihood and calculating the uncertainty of dose estimate.
|
Published |
2019-03 |
Edition : 1 |
Number of pages : 41 |
Technical Committee |
13.280
Radiation protection
|
| ISO 20553:2006 |
Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material |
ISO 20553:2006 specifies the minimum requirements for the design of professional programmes to monitor workers exposed to the risk of internal contamination by radioactive substances and establishes principles for the development of compatible goals and requirements for monitoring programmes.
|
Published |
2006-04 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
13.280
Radiation protection
|
| ISO/CD 20553 |
Radiation protection — Monitoring of workers occupationally exposed to a risk of internal contamination with radioactive material |
|
Under development |
|
Edition : 2 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 20785-1:2006 |
Dosemetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements |
ISO 20785-1:2006 gives the conceptual basis for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft and for the calibration of instruments used for this purpose.
|
Withdrawn |
2006-04 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-1:2012 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements |
ISO 20785:2012 gives the conceptual basis for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft and for the calibration of instruments used for this purpose.
|
Withdrawn |
2012-12 |
Edition : 2 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-1:2020 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 1: Conceptual basis for measurements |
This document specifies the conceptual basis for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft and for the calibration of instruments used for that purpose.
|
Published |
2020-07 |
Edition : 3 |
Number of pages : 27 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-2:2011 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 2: Characterization of instrument response |
ISO 20785-1:2011 specifies methods and procedures for characterizing the responses of devices used for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft. The methods and procedures are intended to be understood as minimum requirements.
|
Withdrawn |
2011-06 |
Edition : 1 |
Number of pages : 36 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-2:2020 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 2: Characterization of instrument response |
This document specifies methods and procedures for characterizing the responses of devices used for the determination of ambient dose equivalent for the evaluation of exposure to cosmic radiation in civilian aircraft. The methods and procedures are intended to be understood as minimum requirements.
|
Published |
2020-07 |
Edition : 2 |
Number of pages : 36 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 2533:1975/Add 2:1997 |
Standard Atmosphere — Addendum 2: Extension to - 5000 m and standard atmosphere as a function of altitude in feet |
|
Published |
1997-11 |
Edition : 1 |
Number of pages : 123 |
Technical Committee |
07.060
Geology. Meteorology. Hydrology
;
17.020
Metrology and measurement in general
;
19.020
Test conditions and procedures in general
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-3:2015 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes |
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
|
Published |
2015-11 |
Edition : 1 |
Number of pages : 16 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO/FDIS 20785-3 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 3: Measurements at aviation altitudes |
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
|
Under development |
|
Edition : 2 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
49.020
Aircraft and space vehicles in general
|
| ISO 20785-4:2019 |
Dosimetry for exposures to cosmic radiation in civilian aircraft — Part 4: Validation of codes |
This document is intended for the validation of codes used for the calculation of doses received by individuals on board aircraft. It gives guidance to radiation protection authorities and code developers on the basic functional requirements which the code fulfils.
Depending on any formal approval by a radiation protection authority, additional requirements concerning the software testing can apply.
|
Published |
2019-05 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
13.280
Radiation protection
;
49.020
Aircraft and space vehicles in general
|
| ISO 20899:2018 |
Water quality — Plutonium and neptunium — Test method using ICP-MS |
This document specifies methods used to determine the concentration of plutonium and neptunium isotopes in water by inductively coupled plasma mass spectrometry (ICP-MS) (239Pu, 240Pu, 241Pu and 237Np). The concentrations obtained can be converted into activity concentrations of the different isotopes[9].
Due to its relatively short half-life and 238U isobaric interference, 238Pu can hardly be measured by this method. To quantify this isotope, other techniques can be used (ICP-MS with collision-reaction cell, ICP-MS/MS with collision-reaction cell or chemical separation). Alpha spectrometry measurement, as described in ISO 13167[10], is currently used[11].
This method is applicable to all types of water having a saline load less than 1 g·l−1. A dilution of the sample is possible to obtain a solution having a saline load and activity concentrations compatible with the preparation and the measurement assembly.
A filtration at 0,45 μm is needed for determination of dissolved nuclides. Acidification and chemical separation of the sample are always needed.
The limit of quantification depends on the chemical separation and the performance of the measurement device.
This method covers the measurement of those isotopes in water in activity concentrations between around[12][13]:
— 1 mBq·l−1 to 5 Bq·l−1 for 239Pu, 240Pu and 237Np;
— 1 Bq·l−1 to 5 Bq·l−1 for 241Pu.
In both cases, samples with higher activity concentrations than 5 Bq·l−1 can be measured if a dilution is performed before the chemical separation.
It is possible to measure 241Pu following a pre-concentration step of at least 1 000.
|
Published |
2018-09 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 21243:2008 |
Radiation protection — Performance criteria for laboratories performing cytogenetic triage for assessment of mass casualties in radiological or nuclear emergencies — General principles and application to dicentric assay |
ISO 21243:2008 is to give an overview of the minimum requirements of process and quality-control components of the cytogenetic response for triage of mass casualties. Cytogenetic triage is the use of chromosome damage to evaluate approximately and rapidly radiation doses received by individuals in order to supplement the early clinical categorization of casualties. ISO 21243:2008 concentrates on organizational aspects of applying the dicentric assay for operation in a triage mode. The technical aspects of the dicentric assay can be found in the ISO 19238, ISO 21243:2008 is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories.
|
Withdrawn |
2008-09 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 3205:1976 |
Preferred test temperatures |
The aim is the rationalize, harmonize and simplify the choice of temperatures in the future. It is permissible to use other temperatures when this is considered essential for technical reasons. At list of additional temperatures taken from international technical documents is given in an annex.
|
Withdrawn |
1976-07 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
19.020
Test conditions and procedures in general
|
| ISO/R 165:1960 |
Flanging test on steel tubes |
|
Withdrawn |
1960-11 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
23.040.10
Iron and steel pipes
;
77.040.10
Mechanical testing of metals
|
| ISO 21243:2022 |
Radiation protection — Performance criteria for laboratories performing initial cytogenetic dose assessment of mass casualties in radiological or nuclear emergencies — General principles and application to dicentric assay |
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).
|
Published |
2022-11 |
Edition : 2 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 21482:2007 |
Ionizing-radiation warning — Supplementary symbol |
ISO 21482:2007 specifies the symbol to warn of the presence of a dangerous level of ionizing radiation from a high-level sealed radioactive source that can cause death or serious injury if handled carelessly. This symbol is not intended to replace the basic ionizing radiation symbol (ISO 361), but to supplement it by providing further information on the danger associated with the source and the necessity for untrained or uninformed members of the public to stay away from it.
This symbol is recommended for use with International Atomic Energy Agency (IAEA) Category 1, 2, and 3 sealed radioactive sources. These sources are defined by the IAEA as having the ability to cause death or serious injuries.
|
Published |
2007-02 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
13.280
Radiation protection
;
01.080.20
Graphical symbols for use on specific equipment
|
| ISO 21909-1:2015 |
Passive neutron dosimetry systems — Part 1: Performance and test requirements for personal dosimetry |
ISO 21909-1:2015 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 MeV[1]. No distinction between the different techniques available in the market place is made in the description of the tests. Only generic distinctions, as disposable or reusable dosemeters for instance, are considered. This part of ISO 21909 gives information for extremity dosimetry, based on recommendations given by ICRU Report 66 in Annex A.
[1] This maximal limit of the energy range is only an order of magnitude. The reference radiation fields used for the performance tests are those defined in ISO 8529-1. This means that the maximal energies could only be 14,8 MeV or 19 MeV. The present standard gives performance requirements to 14,8 MeV which is the typical neutron energy encountered for fusion. For fission spectra, the highest energies are around 20 MeV but the contribution to dose equivalent coming from neutrons with energy higher than 14,8 MeV is negligible.
|
Withdrawn |
2015-12 |
Edition : 1 |
Number of pages : 39 |
Technical Committee |
13.280
Radiation protection
|
| ISO 21909-1:2021 |
Passive neutron dosimetry systems — Part 1: Performance and test requirements for personal dosimetry |
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.
This document gives information for extremity dosimetry in the Annex C, based on recommendations given by ICRU Report 66. This document addresses only neutron personal monitoring and not criticality accident conditions.
The links between this document and ISO 21909-2 are given in Annex A.
|
Published |
2021-12 |
Edition : 2 |
Number of pages : 42 |
Technical Committee |
13.280
Radiation protection
|
| ISO 21909-2:2021 |
Passive neutron dosimetry systems — Part 2: Methodology and criteria for the qualification of personal dosimetry systems in workplaces |
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.
NOTE This document is directed at all stakeholders who are involved: IMSs, accreditation or regulatory bodies, and users of the particular dosimetry (the user is meant as the entity which assigns the dosimetry system to the radiation worker and records the assigned dose.)
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.
The links between ISO 21909-1 and ISO 21909-2 are described in Annex E.
This document only addresses neutron personal monitoring and not criticality accident conditions.
|
Published |
2021-12 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
|
| ISO 22188:2004 |
Monitoring for inadvertent movement and illicit trafficking of radioactive material |
ISO 22188:2004 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 (e.g. 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 ISO 22188:2004, 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. ISO 22188:2004 does not 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 may be done at the borders of a state.
ISO 22188:2004 is applicable to regulatory authorities seeking guidance on implementation of action plans to combat illicit trafficking, to law enforcement agencies (e.g. border guards) to obtain guidelines on recommended monitoring procedures, and to equipment manufacturers in order to understand minimum requirements derived from operational necessities according to ISO 22188:2004.
|
Published |
2004-06 |
Edition : 1 |
Number of pages : 35 |
Technical Committee |
13.280
Radiation protection
|
| ISO/FDIS 22188 |
Monitoring for inadvertent movement and illicit trafficking of radioactive material |
|
Under development |
|
Edition : 2 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 22908:2020 |
Water quality — Radium 226 and Radium 228 — Test method using liquid scintillation counting |
This document specifies the determination of radium-226 (226Ra) and radium-228 (228Ra) activity concentrations in drinking water samples by chemical separation of radium and its measurement using liquid scintillation counting.
Massic activity concentrations of 226Ra and 228Ra which can be measured by this test method utilizing currently available liquid scintillation counters go down to 0,01 Bq/kg for 226Ra and 0,06 Bq/kg for 228Ra for a 0,5 kg sample mass and a 1 h counting time in a low background liquid scintillation counter[8].
The test method can be used for the fast detection of contamination of drinking water by radium in emergency situations.
|
Published |
2020-01 |
Edition : 1 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO/TR 22930-1:2020 |
Evaluating the performance of continuous air monitors — Part 1: Air monitors based on accumulation sampling techniques |
The use of a continuous air monitor (CAM) is mainly motivated by the need to be alerted quickly and in the most accurate way possible with an acceptable false alarm rate when a significant activity concentration value is exceeded, in order to take appropriate measures to reduce exposure of those involved.
The performance of this CAM does not only depend on the metrological aspect characterized by the decision threshold, the limit of detection and the measurement uncertainties but also on its dynamic capacity characterized by its response time as well as on the minimum detectable activity concentration corresponding to an acceptable false alarm rate.
The ideal performance is to have a minimum detectable activity concentration as low as possible associated with a very short response time, but unfortunately these two criteria are in opposition. It is therefore important that the CAM and the choice of the adjustment parameters and the alarm levels be in line with the radiation protection objectives.
The knowledge of a few factors is needed to interpret the response of a CAM and to select the appropriate CAM type and its operating parameters.
Among those factors, it is important to know the half-lives of the radionuclides involved, in order to select the appropriate detection system and its associated model of evaluation.
CAM using filter media accumulation sampling techniques are usually of two types:
a) fixed filter;
b) moving filter.
This document first describes the theory of operation of each CAM type i.e.:
— the different models of evaluation considering short or long radionuclides half-lives values,
— the dynamic behaviour and the determination of the response time.
In most case, CAM is used when radionuclides with important radiotoxicities are involved (small value of ALI). Those radionuclides have usually long half-life values.
Then the determination of the characteristic limits (decision threshold, detection limit, limits of the coverage interval) of a CAM is described by the use of long half-life models of evaluation.
Finally, a possible way to determine the minimum detectable activity concentration and the alarms setup is pointed out.
The annexes of this document show actual examples of CAM data which illustrate how to quantify the CAM performance by determining the response time, the characteristics limits, the minimum detectable activity concentration and the alarms setup.
|
Published |
2020-05 |
Edition : 1 |
Number of pages : 52 |
Technical Committee |
13.280
Radiation protection
|
| ISO/TR 22930-2:2020 |
Evaluating the performance of continuous air monitors — Part 2: Air monitors based on flow-through sampling techniques without accumulation |
The use of a continuous air monitor (CAM) is mainly motivated by the need to be alerted quickly and in the most accurate way possible with an acceptable false alarm rate when significant activity concentration value is exceeded, in order to take appropriate measures to reduce exposure of those involved.
The performance of this CAM does not only depend on the metrological aspect characterized by the decision threshold, the limit of detection and the measurement uncertainties but also on its dynamic capacity characterized by its response time as well as on the minimum detectable activity concentration corresponding to an acceptable false alarm rate.
The ideal performance is to have a minimum detectable activity concentration as low as possible associated with a very short response time, but unfortunately these two criteria are in opposition. It is therefore important that the CAM and the choice of the adjustment parameters and the alarm levels be in line with the radiation protection objectives.
This document describes
— the dynamic behaviour and the determination of the response time,
— the determination of the characteristic limits (decision threshold, detection limit, limits of the coverage interval), and
— a possible way to determine the minimum detectable activity concentration and the alarms setup.
Finally the annexes of this document show actual examples of CAM data which illustrate how to quantify the CAM performance by determining the response time, the characteristics limits, the minimum detectable activity concentration and the alarms setup.
|
Published |
2020-05 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
|
| ISO 23018:2022 |
Group-averaged neutron and gamma-ray cross sections for radiation protection and shielding calculations for nuclear reactors |
This document provides guidance in the preparation, verification, and validation of group-averaged neutron and gamma-ray cross sections for the energy range and materials of importance in radiation protection and shielding calculations for nuclear reactors[1], see also Annex A.
[1] This edition is based on ANSI/ANS-6.1.2-2013[1].
|
Published |
2022-05 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
13.280
Radiation protection
;
27.120.10
Reactor engineering
|
| ISO 10131-2:1997 |
Foldaway beds — Safety requirements and tests — Part 2: Test methods |
|
Published |
1997-08 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
97.140
Furniture
|
| ISO 23588:2023 |
Radiological protection — General requirements for proficiency tests for in vivo radiobioassay |
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.
|
Published |
2023-02 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
13.280
Radiation protection
|
| ISO/TR 24422:2022 |
Development of a water equivalent phantom to measure the physical characteristics of specific radiosurgery treatment devices |
A water phantom is used to ensure the accurate measurement of absorbed dose delivered by a radiation therapy machine as well as standardizing the dose distribution produced by the radiation therapy device.
This document describes a detailed procedure for the construction and calibration of a polystyrene phantom and the results of its use in measuring the absorbed dose profile around the mechanical centre of a radiosurgery medical device, the full width at half maximum (FWHM) of the field and the physical penumbra at the mechanical centre, as well as the associated uncertainties.
According to IAEA TRS-483 document, the most common design recommended in Gamma Knife® system is a hemisphere atop a water filled or compact polystyrene cylinder, and when using a polystyrene phantom, the measurement depth of the absorbed dose to water is reported to be the centre of the hemisphere with the radius of 8 cm.
This document mainly describes the procedure for measuring the absorbed dose distribution around the mechanical centre of Gamma Knife® and obtaining the FWHM and penumbra from it. The developed phantom is made of polystyrene and has a hemispherical shape in accordance with the design suggested in IAEA TRS-483.
This type of phantom is specific and adapted only for the Gamma Knife® radiosurgery facilities (PerfexionTM and IconTM models) and does not apply to general dosimetry protocols in radiotherapy facilities that use a small radiation field to treat a disease such as LINAC or Cyberknife.
Considering that the type of medical device corresponds to treatment using external beam radiotherapy following small static fields, this technical report follows the recommendations published in the IAEA TRS‑483.
|
Published |
2022-12 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
13.280
Radiation protection
|
| ISO/DIS 24426 |
Radiological protection — Format of input data for the statistical description of dose records of individuals monitored for occupational exposure to ionizing radiation |
|
Under development |
|
Edition : 1 |
Number of pages : 20 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO/CD 24427 |
Radiological protection — Medical proton accelerators — Requirements and recommendations for shielding design and evaluation |
This International Standard is applicable to radiation shielding design and evaluation work for medical proton accelerators with nominal energies of the beam ranging from 70 MeV to 250 MeV, with subsystem such as beamlines, energy selection system (for cyclotron) and nozzle components.
The radiation protection requirements and recommendations given in this international standard 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 and interactions between stakeholders, source terms 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), the radiological monitoring (measurements) and area control.
|
Under development |
|
Edition : 1 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO/DIS 24434-1 |
Radiological protection — Radiological monitoring for emergency workers and population following nuclear/radiological incidents — Part 1: General principles |
|
Under development |
|
Edition : 1 |
Number of pages : 80 |
Technical Committee |
13.100
Occupational safety. Industrial hygiene
;
13.200
Accident and disaster control
;
13.280
Radiation protection
|
| ISO/DIS 24588 |
Protective clothing — Personal protective ensembles for use against chemical, biological, radiological and nuclear (CBRN) agents — Classification, performance requirements and test methods |
|
Under development |
|
Edition : 1 |
Number of pages : 45 |
Technical Committee |
13.280
Radiation protection
;
13.340.10
Protective clothing
|
| ISO 27048:2011 |
Radiation protection — Dose assessment for the monitoring of workers for internal radiation exposure |
ISO 27048:2011 specifies the minimum requirements for the evaluation of data from the monitoring of workers occupationally exposed to the risk of internal contamination by radioactive substances. It presents procedures and assumptions for the standardised interpretation of monitoring data, in order to achieve acceptable levels of reliability. Those procedures allow the quantification of exposures for the documentation of compliance with regulations and radiation protection programmes. Limits are set for the applicability of the procedures in respect of the dose levels above which more sophisticated methods will have to be applied.
ISO 27048:2011 addresses the following: procedures for dose assessment based on reference levels for routine and special monitoring programmes; assumptions for the selection of dose-critical parameter values; criteria for determining the significance of monitoring results; interpretation of workplace monitoring results; uncertainties arising from sampling, measurement techniques and working conditions; the special topics of interpretation of multiple data arising from different measurement methods at different times, handling data below the decision threshold, rogue data, and calculation of doses to the embryo/foetus and infant; reporting/documentation; quality assurance.
It is not applicable to the following: dosimetry for litigation cases; modelling for the improvement of internal dosimetry; the potential influence of decorporation measures (e.g. administration of chelating agents); the investigation of the causes or implications of an exposure; dosimetry for contaminated wounds.
|
Published |
2011-01 |
Edition : 1 |
Number of pages : 76 |
Technical Committee |
13.280
Radiation protection
|
| ISO 28057:2014 |
Dosimetry with solid thermoluminescence detectors for photon and electron radiations in radiotherapy |
ISO 28057:2014 describes rules for the procedures, applications, and systems of thermoluminescence dosimetry (TLD) for dose measurements according to the probe method. It is particularly applicable to solid "TL detectors", i.e. rods, chips, and microcubes, made from LiF:Mg,Ti or LiF:Mg,Cu,P in crystalline or polycrystalline form. The probe method encompasses the arrangement, particularly in a water phantom or in a tissue-equivalent phantom, of single TL detectors or of "TL probes", i.e. sets of TL detectors arranged in thin-walled polymethyl methacrylate (PMMA) casings.
The purpose of these rules is to guarantee the reliability and the accuracy indispensable in clinical dosimetry when applied on or in the patient or phantom. ISO 28057:2014 applies to dosimetry in teletherapy with both photon radiation from 20 keV to 50 MeV and electron radiation from 4 MeV to 25 MeV, as well as in brachytherapy with photon-emitting radionuclides. These applications are complementary to the use of ionization chambers.
|
Withdrawn |
2014-03 |
Edition : 1 |
Number of pages : 40 |
Technical Committee |
13.280
Radiation protection
|
| ISO 28057:2019 |
Clinical dosimetry — Dosimetry with solid thermoluminescence detectors for photon and electron radiations in radiotherapy |
This document describes rules for the procedures, applications, and systems of thermoluminescence dosimetry (TLD) for dose measurements according to the probe method. It is particularly applicable to solid "TL detectors", i.e. rods, chips, and microcubes, made from LiF:Mg,Ti or LiF:Mg,Cu,P in crystalline or polycrystalline form. It is not applicable to LiF powders because their use requires special procedures. The probe method encompasses the arrangement, particularly in a water phantom or in a tissue-equivalent phantom, of single TL detectors or of "TL probes", i.e. sets of TL detectors arranged in thin-walled polymethyl methacrylate (PMMA) casings.
The purpose of these rules is to guarantee the reliability and the accuracy indispensable in clinical dosimetry when applied on or in the patient or phantom. This document applies to dosimetry in teletherapy with both photon radiation from 20 keV to 50 MeV and electron radiation from 4 MeV to 25 MeV, as well as in brachytherapy with photon-emitting radionuclides. These applications are complementary to the use of ionization chambers.
|
Published |
2019-07 |
Edition : 2 |
Number of pages : 41 |
Technical Committee |
13.280
Radiation protection
|
| ISO 28077:2006 |
Photocarcinogenesis action spectrum (non-melanoma skin cancers) |
ISO/CIE 28077:2006 specifies the action spectrum for photocarcinogenesis of non-melanoma skin cancers.
|
Withdrawn |
2006-12 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
13.280
Radiation protection
;
17.180.20
Colours and measurement of light
|
| ISO/CIE 28077:2016 |
Photocarcinogenesis action spectrum (non-melanoma skin cancers) |
ISO/CIE 28077:2016 specifies the action spectrum for photocarcinogenesis of non-melanoma skin cancers.
|
Published |
2016-10 |
Edition : 2 |
Number of pages : 7 |
Technical Committee |
13.280
Radiation protection
;
17.180.20
Colours and measurement of light
|
| ISO/CIE DIS 28077 |
Photocarcinogenesis action spectrum (non-melanoma skin cancers) |
ISO/CIE 28077:2016 specifies the action spectrum for photocarcinogenesis of non-melanoma skin cancers.
|
Under development |
|
Edition : 3 |
Number of pages : 7 |
Technical Committee |
13.280
Radiation protection
;
17.180.20
Colours and measurement of light
|
| ISO 28218:2010 |
Radiation protection — Performance criteria for radiobioassay |
This International Standard provides criteria for quality assurance and control, and evaluation of performance of radiobioassay service laboratories.
Criteria and guidance for in vivo radiobioassay and in vitro radiobioassay are given in separate clauses.
The following are within the scope of this International Standard:
the accuracy of
in vivo measurements of activity and quantities of selected important radionuclides in test phantoms, and
in vitro measurements of activity and quantities of selected important radionuclides in test samples;
minimal requirements for detection limit;
minimum testing levels and testing ranges;
requirements for reporting radiobioassay results by service laboratories;
quality assurance in service laboratories;
quality control in service laboratories;
protocol for reporting test evaluations by service laboratories to the testing laboratory;
default procedures when the service laboratory customer does not specify the performance criteria;
applications of y# for different methods (see Annexes A and B).
The following are not within the scope of this International Standard:
detailed radiochemical methods for separating radionuclides from biological samples;
detailed procedures for in vivo and in vitro radioactivity measurements;
biokinetic data and mathematical models for converting radiobioassay results into dose (dose assessment);
procedures for the preparation and distribution of test samples and phantoms by the testing laboratories.
|
Published |
2010-10 |
Edition : 1 |
Number of pages : 45 |
Technical Committee |
13.280
Radiation protection
|
| ISO 4677-1:1985 |
Atmospheres for conditioning and testing — Determination of relative humidity — Part 1: Aspirated psychrometer method |
The method specified applies for temperatures within the range from 5 to 80 °C. The property is determined with an uncertainty either not exceeding 3 % r. h. or not exceeding 3 % r. h., depending on the uncertainty in the value obtained for the wet-bulb temperature depression and on whether or not the dry-bulb temperature exceeds 40 °C.
|
Withdrawn |
1985-10 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
19.020
Test conditions and procedures in general
|
| ISO/R 166:1960 |
Drift expanding test on steel tubes |
|
Withdrawn |
1960-11 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
23.040.10
Iron and steel pipes
;
77.040.10
Mechanical testing of metals
|
| ISO 29661:2012 |
Reference radiation fields for radiation protection — Definitions and fundamental concepts |
ISO 29661:2012 defines terms and fundamental concepts for the calibration of dosemeters and equipment used for the radiation protection dosimetry of external radiation -- in particular, for beta, neutron and photon radiation. It defines the measurement quantities for radiation protection dosemeters and doserate meters and gives recommendations for establishing these quantities. For individual monitoring, it covers whole body and extremity dosemeters (including those for the skin and the eye lens), and for area monitoring, portable and installed dosemeters. Guidelines are given for the calibration of dosemeters and doserate meters used for individual and area monitoring in reference radiation fields. Recommendations are made for the position of the reference point and the phantom to be used for personal dosemeters.
ISO 29661:2012 also deals with the determination of the response as a function of radiation quality and angle of radiation incidence.
ISO 29661:2012 is intended to be used by calibration laboratories and manufacturers.
|
Published |
2012-09 |
Edition : 1 |
Number of pages : 35 |
Technical Committee |
13.280
Radiation protection
|
| ISO 29661:2012/Amd 1:2015 |
Reference radiation fields for radiation protection — Definitions and fundamental concepts — Amendment 1: Reference point of personal dosemeters |
|
Published |
2015-12 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
13.280
Radiation protection
|
| ISO Guide 4:1975 |
Preparation of standard methods of measuring performance of consumer goods (SMMP) |
|
Withdrawn |
1975-12 |
Edition : 1 |
|
Technical Committee |
19.020
Test conditions and procedures in general
;
03.080.30
Services for consumers
|
| ISO Guide 12:1977 |
Comparative testing of consumer products |
|
Withdrawn |
1977-02 |
Edition : 1 |
|
Technical Committee |
19.020
Test conditions and procedures in general
;
03.080.30
Services for consumers
|
| ISO/IEC Guide 45:1985 |
Withdrawn |
|
Withdrawn |
1985-10 |
Edition : 1 |
|
Technical Committee |
19.020
Test conditions and procedures in general
;
03.120.20
Product and company certification. Conformity assessment
|
| ISO/IEC Guide 46:1985 |
Comparative testing of consumer products and related services — General principles |
The principles are applicable to consumer products, services and a combination of both. They may usefully be followed by bodies and associations which conduct comparative testing programmes. The purpose of this Guide is to enable meaningful test results and information to be presented in a way which will help consumers and others to make an informed choice suitable to their own needs. The notes offer some but not all the means of applying the principles.
|
Withdrawn |
1985-11 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
19.020
Test conditions and procedures in general
;
03.080.30
Services for consumers
|
| ISO/IEC Guide 46:2017 |
Comparative testing of consumer products and related services — General principles |
ISO/IEC Guide 46:2017 establishes general principles for the conduct of comparative testing of products and services for the information of consumers.
It does not cover anti-counterfeiting or conformity assessment.
|
Published |
2017-02 |
Edition : 2 |
Number of pages : 5 |
Technical Committee |
19.020
Test conditions and procedures in general
;
03.080.30
Services for consumers
|
| ISO 554:1976 |
Standard atmospheres for conditioning and/or testing — Specifications |
Specifies three atmospheres approximated to the natural environmental conditions. However, it is desirable to use only one of these.
|
Published |
1976-08 |
Edition : 1 |
Number of pages : 1 |
Technical Committee |
19.020
Test conditions and procedures in general
|
| ISO 558:1980 |
Conditioning and testing — Standard atmospheres — Definitions |
Defines three types. They are often required in order to investigate the effect of extreme climatic conditions on test specimens. Such atmospheres often differ greatly from ordinary ambient conditions.
|
Published |
1980-09 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
19.020
Test conditions and procedures in general
|
| ISO 2533:1975 |
Standard Atmosphere |
Specifies the characteristics of the Atmosphere Type ISO which is applicable to planning under identical conditions, to test results end elements. Permits the unification in the range of tests and calibration of instruments. Is recommended for treatment of results of observations of geophysics and meteorology.
|
Published |
1975-05 |
Edition : 1 |
Number of pages : 108 |
Technical Committee |
07.060
Geology. Meteorology. Hydrology
;
17.020
Metrology and measurement in general
;
19.020
Test conditions and procedures in general
;
49.020
Aircraft and space vehicles in general
|
| ISO 89:1974 |
Steel — Tensile testing of wire |
|
Withdrawn |
1974-08 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
77.040.10
Mechanical testing of metals
;
77.140.65
Steel wire, wire ropes and link chains
|
| ISO 4677-2:1985 |
Atmospheres for conditioning and testing — Determination of relative humidity — Part 2: Whirling psychrometer method |
The method specified applies for temperatures within the range from 5 to 80 °C. The property is determined with an uncertainty not exceeding 3 % r. h. The method is restricted to wet-bulb temperatures not lower than 1 C, dry-bulb temperatures not higher than 80 °C, and pressures not differing from standard atmospheric pressure by more than 30 %.
|
Withdrawn |
1985-10 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
19.020
Test conditions and procedures in general
|
| ISO/PRF 22804 |
Marine technology — General technical requirement of marine Conductivity-Temperature-Depth (CTD) measuring instrument |
|
Under development |
|
Edition : 1 |
|
Technical Committee |
19.040
Environmental testing
;
47.020.99
Other standards related to shipbuilding and marine structures
|
| ISO/TTA 2:1997 |
Tensile tests for discontinuously reinforced metal matrix composites at ambient temperatures |
This document is an outline procedure for the tensile testing of discontinuously reinforced metal matrix composites (MMC) and defines the mechanical properties which tan be determined at ambient temperature, such as Young's modulus, proportional limits, proof stress, tensile strength and elongation to failure. It follows the European Standard EN 10002 for the tensile testing of metals and its sister document for Aerospace materials EN 20024 Part 1. [refs 1 and 2 in annex C.]
|
Withdrawn |
1997-04 |
Edition : 1 |
Number of pages : 16 |
Technical Committee |
19.060
Mechanical testing
|
| ISO/TTA 5:2006 |
Code of practice for creep/fatigue testing of cracked components |
The scope of ISO/TTA 5:2006 is to recommend and establish standardized techniques for measuring and analysing Creep Crack Initiation (CCI), Creep Crack Growth (CCG), and Creep Fatigue Crack Growth (CFCG) characteristics using a wide range of pre-cracked standard and non-standard "feature" geometries.
|
Withdrawn |
2006-12 |
Edition : 1 |
Number of pages : 77 |
Technical Committee |
19.060
Mechanical testing
|
| ISO/TTA 5:2007 |
Code of practice for creep/fatigue testing of cracked components |
ISO/TTA 5:2007 recommends and establishes standardized techniques for measuring and analysing Creep Crack Initiation (CCI), Creep Crack Growth (CCG), and Creep Fatigue Crack Growth (CFCG) characteristics, using a wide range of pre-cracked standard and non-standard "feature" geometries.
|
Published |
2007-10 |
Edition : 2 |
Number of pages : 78 |
Technical Committee |
19.060
Mechanical testing
|
| ISO/R 79:1968 |
Brinell hardness test for steel |
|
Withdrawn |
1968-03 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 80:1968 |
Rockwell hardness test (B and C scales) for steel |
|
Withdrawn |
1968-02 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 81:1967 |
Vickers hardness test for steel (Load 5 to 100 kgf) |
|
Withdrawn |
1967-11 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 82:1974 |
Steel — Tensile testing |
|
Withdrawn |
1974-08 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 83:1976 |
Steel — Charpy impact test (U-notch) |
Specifies the charpy impact method using U-notch test pieces. Determines the impact strength of steel by breaking by one blow from a swinging pendulum, under conditions defined hereafter, a test piece resting on two supports and determining the energy absorbed.
|
Withdrawn |
1976-11 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 84:1959 |
Izod impact test for steel |
|
Withdrawn |
1959-02 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 85:1959 |
Bend test for steel |
|
Withdrawn |
1959-02 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 86:1974 |
Steel — Tensile testing of sheet and strip less than 3 mm and not less than 0,5 mm thick |
|
Withdrawn |
1974-08 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
77.040.10
Mechanical testing of metals
;
77.140.50
Flat steel products and semi-products
|
| ISO/R 87:1959 |
Simple bend testing of steel sheet and strip less than 3 mm thick |
|
Withdrawn |
1959-02 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
77.040.10
Mechanical testing of metals
;
77.140.50
Flat steel products and semi-products
|
| ISO/R 88:1959 |
Reverse bend testing of steel sheet and strip less than 3 mm thick |
|
Withdrawn |
1959-02 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
77.040.10
Mechanical testing of metals
;
77.140.50
Flat steel products and semi-products
|
| ISO 148-1:2016 |
Metallic materials — Charpy pendulum impact test — Part 1: Test method |
ISO 148-1:2016 specifies the Charpy (V-notch and U-notch) pendulum impact test method for determining the energy absorbed in an impact test of metallic materials. This part of ISO 148 does not cover instrumented impact testing, which is specified in ISO 14556.
Annexes B and C are based on ASTM E23 and are used with the permission of ASTM International, 100 Barr Harbor Drive, P.O. Box C700, West Conshohocken, PA 19428-2959, USA.
|
Published |
2016-10 |
Edition : 3 |
Number of pages : 29 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 148-2:1998 |
Metallic materials — Charpy pendulum impact test — Part 2: Verification of test machines |
|
Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 148-2:2008 |
Metallic materials — Charpy pendulum impact test — Part 2: Verification of testing machines |
ISO 148-2:2008 covers the verification of the constructional elements of pendulum-type impact testing machines. It is applicable to machines with 2 mm or 8 mm strikers used for pendulum impact tests carried out, for instance, in accordance with ISO 148-1.
It can analogously be applied to pendulum impact testing machines of various capacities and of different design.
Impact machines used for industrial, general or research laboratory testing of metallic materials in accordance with ISO 148-2:2008 are referred to as industrial machines. Those with more stringent requirements are referred to as reference machines. Specifications for the verification of reference machines are found in ISO 148-3.
ISO 148-2:2008 describes two methods of verification: a direct method and an indirect method.
|
Withdrawn |
2008-12 |
Edition : 2 |
Number of pages : 38 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 148-2:2016 |
Metallic materials — Charpy pendulum impact test — Part 2: Verification of testing machines |
ISO 148-2:2016 covers the verification of pendulum-type impact testing machines, in terms of their constructional elements, their overall performance and the accuracy of the results they produce. It is applicable to machines with 2 mm or 8 mm strikers used for pendulum impact tests carried out, for instance, in accordance with ISO 148‑1.
It can be applied to pendulum impact testing machines of various capacities and of different design.
Impact machines used for industrial, general or research laboratory testing of metallic materials in accordance with this part of ISO 148 are referred to as industrial machines. Those with more stringent requirements are referred to as reference machines. Specifications for the verification of reference machines are found in ISO 148‑3.
ISO 148-2:2016 describes two methods of verification.
a) The direct method, which is static in nature, involves measurement of the critical parts of the machine to ensure that it meets the requirements of this part of ISO 148. Instruments used for the verification and calibration are traceable to national or international standards.
b) The indirect method, which is dynamic in nature, uses reference test pieces to verify points on the measuring scale for absorbed energy. The requirements for the reference test pieces are found in ISO 148‑3.
A pendulum impact testing machine is not in compliance with this part of ISO 148 until it has been verified by both the direct and indirect methods and meets the requirements of Clause 6 and Clause 7.
ISO 148-2:2016 describes how to assess the different components of the total energy absorbed in fracturing a test piece. This total absorbed energy consists of
- the energy needed to fracture the test piece itself, and
- the internal energy losses of the pendulum impact testing machine performing the first half-cycle swing from the initial position.
NOTE Internal energy losses are due to the following:
- air resistance, friction of the bearings of the rotation axis and of the indicating pointer of the pendulum which can be determined by the direct method (see 6.4.5);
- shock of the foundation, vibration of the frame and pendulum for which no suitable measuring methods and apparatus have been developed.
|
Published |
2016-10 |
Edition : 3 |
Number of pages : 38 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 148-3:1998 |
Metallic materials — Charpy pendulum impact test — Part 3: Preparation and characterization of Charpy V reference test pieces for verification of test machines |
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Withdrawn |
1998-12 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 148-3:2008 |
Metallic materials — Charpy pendulum impact test — Part 3: Preparation and characterization of Charpy V-notch test pieces for indirect verification of pendulum impact machines |
ISO 148-3:2008 covers the requirements, preparation and methods for qualifying test pieces used for the indirect verification of pendulum impact testing machines in accordance with ISO 148-2.
ISO 148-3:2008 specifies notched test pieces with nominal dimensions identical to those specified in ISO 148-1; however, the tolerances are more stringent.
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Withdrawn |
2008-12 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 148-3:2016 |
Metallic materials — Charpy pendulum impact test — Part 3: Preparation and characterization of Charpy V-notch test pieces for indirect verification of pendulum impact machines |
ISO 148-3:2016 specifies the requirements, preparation and methods for qualifying test pieces used for the indirect verification of pendulum impact testing machines in accordance with ISO 148‑2.
It specifies notched test pieces with nominal dimensions identical to those specified in ISO 148‑1; however, the tolerances are more stringent.
NOTE 1 The chemical composition or heat treatment, or both, are varied according to the energy level desired.
NOTE 2 Reference test pieces are qualified on reference pendulum impact testing machines which are also described in this part of ISO 148.
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Published |
2016-10 |
Edition : 3 |
Number of pages : 18 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 148:1983 |
Steel — Charpy impact test (V-notch) |
Specifies the charpy impact method using V-notch test pieces. Determines the impact strength of steel by breaking by one blow from a swinging pendulum, under conditions defined hereafter, a test piece resting on two supports and determining the energy absorbed.
|
Withdrawn |
1983-05 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 149:1960 |
Modified Erichsen cupping test for steel sheet and strip |
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Withdrawn |
1960-02 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
77.040.10
Mechanical testing of metals
;
77.140.50
Flat steel products and semi-products
|
| ISO 204:2009 |
Metallic materials — Uniaxial creep testing in tension — Method of test |
ISO 204:2009 specifies the method for the uninterrupted and interrupted creep tests and defines the properties of metallic materials which can be determined from these tests, in particular the creep elongation and the time of creep rupture, at a specified temperature.
The stress rupture test is also covered, as is the testing of notched test pieces.
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Withdrawn |
2009-06 |
Edition : 2 |
Number of pages : 42 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 204:2018 |
Metallic materials — Uniaxial creep testing in tension — Method of test |
This document specifies the methods for
a) uninterrupted creep tests with continuous monitoring of extension,
b) interrupted creep tests with periodic measurement of elongation,
c) stress rupture tests where normally only the time to fracture is measured,
d) a test to verify that a predetermined time can be exceeded under a given force, with the elongation or extension not necessarily being reported.
NOTE A creep test can be continued until fracture has occurred or it can be stopped before fracture.
|
Published |
2018-08 |
Edition : 3 |
Number of pages : 53 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/FDIS 204 |
Metallic materials — Uniaxial creep testing in tension — Method of test |
|
Under development |
|
Edition : 4 |
Number of pages : 48 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 205:1961 |
Determination of proof stress and proving test for steel at elevated temperature |
|
Withdrawn |
1961-12 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 206:1961 |
Creep stress rupture testing of steel at elevated temperatures |
Applies to those tests in which the time for stress rupture is measured under tensile creep stress at elevated temperatures to tests in single machines and to each test in multiple testing machines.
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Withdrawn |
1961-06 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 373:1964 |
General principles for fatigue testing of metals |
|
Withdrawn |
1964-08 |
Edition : 1 |
Number of pages : 15 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 374:1964 |
Ring expanding test on steel tubes |
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Withdrawn |
1964-08 |
Edition : 1 |
Number of pages : 1 |
Technical Committee |
23.040.10
Iron and steel pipes
;
77.040.10
Mechanical testing of metals
|
| ISO 375:1974 |
Steel — Tensile testing of tubes |
|
Withdrawn |
1974-08 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
23.040.10
Iron and steel pipes
;
77.040.10
Mechanical testing of metals
|
| ISO 376:1987 |
Metallic materials — Calibration of force-proving instruments used for the verification of uniaxial testing machines |
|
Withdrawn |
1987-06 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/R 376:1964 |
Calibration of elastic proving devices |
|
Withdrawn |
1964-08 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 376:1999 |
Metallic materials — Calibration of force-proving instruments used for the verification of uniaxial testing machines |
|
Withdrawn |
1999-08 |
Edition : 2 |
Number of pages : 20 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 376:2004 |
Metallic materials — Calibration of force-proving instruments used for the verification of uniaxial testing machines |
ISO 376:2004 covers the calibration of force-proving instruments used for the static verification of uniaxial testing machines (e.g. tension/compression testing machines) and describes a procedure for classifying these instruments.
ISO 376:2004 generally applies to force-proving instruments in which the force is determined by measuring the elastic deformation of a loaded member or a quantity which is proportional to it.
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Withdrawn |
2004-11 |
Edition : 3 |
Number of pages : 20 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 376:2011 |
Metallic materials — Calibration of force-proving instruments used for the verification of uniaxial testing machines |
ISO 376:2011 specifies a method for the calibration of force-proving instruments used for the static verification of uniaxial testing machines (e.g. tension/compression testing machines) and describes a procedure for the classification of these instruments.
It is applicable to force-proving instruments in which the force is determined by measuring the elastic deformation of a loaded member or a quantity which is proportional to it.
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Published |
2011-06 |
Edition : 4 |
Number of pages : 30 |
Technical Committee |
77.040.10
Mechanical testing of metals
|