| Name |
Description |
Abstract |
Status |
Publication date |
Edition |
Number of pages |
Technical committee |
ICS |
| ISO/TR 4826:1979 |
Sealed radioactive sources — Leak test methods |
The methods described are primarily in support to ISO 2919; to publish them as part of ISO 2919 was not yet possible because acceptance levels could not yet be specified. They are primarily applicable to prototype testing but may also be used for production and other tests. For the particle situation it is necessary to select from them the most suitable test or a combination of tests. The tests are made by radioactive means (wipe or immersion tests) or by non-radioactive means (bubble, helium pressurization or water pressurization tests).
|
Withdrawn |
1979-02 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
13.280
Radiation protection
|
| ISO 6961:1982 |
Long-term leach testing of solidified radioactive waste forms |
Provided to measure the resistance to leaching of the solidified materials: glass, glass-ceramics, ceramics, bitumen, cement, concrete, plastics, the test being aimed at the comparison of different kinds or compositions, intercomparison between test results from different laboratories on one product or on products of different processes. It is not required to carry out tests in all possible combinations of variables but one appropriate set of standard conditions should be met.
|
Withdrawn |
1982-10 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
13.280
Radiation protection
;
13.030.30
Special wastes
|
| ISO 6962:1982 |
Standard method for testing the long term alpha irradiation stability of solidified high-level radioactive waste forms |
Specifies a method designed to check the long-term stability of a solid to alpha disintegration by detection of all modifications in the properties of an irradiated sample. The solid is borosilicate glass or, as an alternative, ceramics or glass-ceramics and a two-phase mixture of glass beads dispersed in a metal matrix, made from adequate (stable) fission product elements spiked with appropriate tracers.
|
Withdrawn |
1982-05 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
13.280
Radiation protection
;
13.030.30
Special wastes
|
| ISO 6962:2004 |
Nuclear energy — Standard method for testing the long-term alpha irradiation stability of matrices for solidification of high-level radioactive waste |
ISO 6962:2004 specifies a method designed to check the long-term stability of a solid to alpha disintegration by detection of all modifications in the properties of an irradiated sample.
The material favoured hitherto is a borosilicate glass, but possible alternatives include ceramics, glass-ceramics or other glass compositions.
|
Published |
2004-07 |
Edition : 2 |
Number of pages : 8 |
Technical Committee |
13.280
Radiation protection
;
13.030.30
Special wastes
|
| ISO 7205:1986 |
Radionuclide gauges — Gauges designed for permanent installation |
Establishes the following characteristics: a classification of the gauges and shielding devices, technical construction and performance requirements for radiation protection when using a radioactive source, control and test methods to verify the compliance with those requirements, indications to be shown on the gauges. Does not apply to gauges which are not subject to general rules regarding supply and possession of artificial radionuclides nor to ion generators.
|
Withdrawn |
1986-12 |
Edition : 1 |
Number of pages : 15 |
Technical Committee |
13.280
Radiation protection
|
| ISO 7212:1986 |
Enclosures for protection against ionizing radiation — Lead shielding units for 50 mm and 100 mm thick walls |
Specifies the properties of the various lead units used in the construction of shielded enclosures: basic units (bricks, posts) and functional units (aperture bricks, windows, sphere units, plugs and reducing units). Only one and two chevron bricks are standardized. The units are classified into 3 categories: standardized units; units which are either used very infrequently or for very specialized purposes, or are used very frequently in one country and it is felt that this use will become more widespread; units which are acceptable for a transition period.
|
Published |
1986-06 |
Edition : 1 |
Number of pages : 55 |
Technical Committee |
13.280
Radiation protection
|
| ISO 7503-1:1988 |
Evaluation of surface contamination — Part 1: Beta-emitters (maximum beta energy greater than 0,15 MeV) and alpha-emitters |
Applies to surfaces of equipment and facilities, containers of radioactive materials and sealed sources, does not apply to the skin and contamination of clothing. Gives direct and indirect methods of measurement (the latter by means of smear tests). Is restricted to beta- and alpha-emitters, the production rate of which, with regard to beta-particles plus monoenergetic electrons and alpha-particles resp., is near to 100 particles per 100 decays. Evaluation of tritium surface contamination is dealt with in ISO 7503-2, other radionuclides of practical importance will be dealt with in a future standard.
|
Withdrawn |
1988-08 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
13.280
Radiation protection
|
| ISO 7503-1:2016 |
Measurement of radioactivity — Measurement and evaluation of surface contamination — Part 1: General principles |
ISO 7503 (all parts) and ISO 8769 are addressed to the people responsible for determining the radioactivity present on solid surfaces. ISO 7503 is published in three parts and can be used jointly or separately according to needs.
ISO 7503-1:2016 relates to the assessment of surface contamination by direct and indirect measurements and the calibration of the associated instrumentation.
The standard applies to alpha-, beta- and photon emitters and is intended for use by hospitals, universities, police, or industrial establishments. The standard also can be used in the assessment of activity on trucks, containers, parcels, equipment and is applicable in any organization which handles radioactive materials. Generally, it is applicable to well defined flat surfaces where direct methods are applicable, however, it can also be used for surfaces which are not flat and where indirect wipe tests would be appropriate. These investigations may be carried out on containers, inaccessible areas, non-flat areas where wipe tests can be used. This part of ISO 7503 may be useful in emergency situations, i.e. in nuclear accidents where health physics professionals would be involved.
ISO 7503-1:2016 does not apply to the evaluation of contamination of the skin, of clothing and of loose material such as gravel.
NOTE The test method using wipe-test samples for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-2. The calibration of instruments for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-3.
|
Published |
2016-01 |
Edition : 2 |
Number of pages : 26 |
Technical Committee |
13.280
Radiation protection
|
| ISO 7503-2:1988 |
Evaluation of surface contamination — Part 2: Tritium surface contamination |
Applies to surfaces of equipment and facilities, containers of radioactive materials and sealed sources, does not apply to the skin and contamination of clothing. Gives a method of direct measurement and an indirect method for removable surface contamination. Evaluation of surface contaminations from beta-emitters (maximum beta energy greater than 0,15 MeV) and alpha-emitters is dealt with in ISO 7503-1, other radionuclides of practical importance will be dealt with in a future standard.
|
Withdrawn |
1988-08 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
13.280
Radiation protection
|
| ISO 7503-2:2016 |
Measurement of radioactivity - Measurement and evaluation of surface contamination — Part 2: Test method using wipe-test samples |
ISO 7503 (all parts) and ISO 8769 are addressed to the people responsible for measuring the radioactivity present on solid surfaces.
ISO 7503-2:2016 applies to the evaluation of contamination on surfaces in terms of activity per unit area by an indirect method of measurement.
ISO 7503-2:2016 is applicable to well-defined surfaces, such as those of equipment and facilities, containers of radioactive materials, sealed sources and buildings or land.
ISO 7503-2:2016 can be used for laboratory and equipment/installation control and for remediation and monitoring activities to comply with release criteria.
ISO 7503-2:2016 also refers to institutions/authorities controlling nuclear material transports or material/equipment clearance according to national legislation guideline values or international convention limits.
ISO 7503-2:2016 does not apply to contamination of the skin, clothing or loose material, such as gravel.
NOTE Direct evaluation of surface contamination from alpha-emitters, beta-emitters and photon emitters is dealt with in ISO 7503-1. The calibration of instruments for the evaluation of radioactive surface contaminations is dealt with in ISO 7503-3.
|
Published |
2016-01 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
13.280
Radiation protection
|
| ISO 7503-3:1996 |
Evaluation of surface contamination — Part 3: Isomeric transition and electron capture emitters, low energy beta-emitters (E bêtamax less than 0,15 MeV) |
Applicable to the evaluation of contamination on surfaces of facilities and equipment, containers of radioactive materials and sealed sources by low energy beta-emitters (<0,15 MeV) in terms of activity per unit area. Does not apply to the evaluation of contamination of skin and clothing.
|
Withdrawn |
1996-11 |
Edition : 1 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
|
| ISO 21909:2005/Cor 1:2007 |
Passive personal neutron dosemeters — Performance and test requirements — Technical Corrigendum 1 |
|
Withdrawn |
2007-10 |
Edition : 1 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 7503-3:2016 |
Measurement of radioactivity — Measurement and evaluation of surface contamination — Part 3: Apparatus calibration |
ISO 7503 and ISO 8769 are addressed to the people responsible for determining the radioactivity present on solid surfaces.
ISO 7503-3:2016 applies to the evaluation of contamination on surfaces in terms of activity per unit area by direct and indirect methods of measurement and deals with the complex aspects of instrument calibration.
ISO 7503-3:2016 is applicable to well-defined surfaces, such as those of equipment and facilities, containers of radioactive materials, sealed sources, and buildings or land.
ISO 7503-3:2016 can be used for laboratory and equipment/installation control and for remediation and monitoring activities to comply with release criteria.
This part of ISO 7503 also refers to the following:
- calibration laboratories or institutions dealing with radionuclides with complex emission characteristics or radionuclides for which no reference calibration sources are available;
- institutions confronted with the task to evaluate surface contaminations consisting of a radionuclide mixture;
- institutions/authorities controlling nuclear material transports or material/equipment clearance according to national legislation guideline values or international convention limits.
ISO 7503-3:2016 does not apply to contamination of the skin, clothing, or loose material, such as gravel.
NOTE Direct evaluation of surface contamination from alpha-emitters, beta-emitters and photon emitters is dealt with in ISO 7503‑1. The test method using wipe-test samples for the evaluation of radioactive surface contaminations is dealt with in ISO 7503‑2.
|
Published |
2016-01 |
Edition : 2 |
Number of pages : 64 |
Technical Committee |
13.280
Radiation protection
|
| ISO 8194:1987 |
Radiation protection — Clothing for protection against radioactive contamination — Design, selection, testing and use |
Gives the characterisitcs of two types of clothing: ventilated-pressurized garments and unventilated-unpressurized garments. These characteristics include the manufacture materials, design and size, accessories, breathing air supply and internal ventilation. Annex A describes a test method according to which any new type of garment can be assigned a protection factor that makes it easier for the user to make a choice. Annexes B and C give methods for measuring leak tightness and air supply flow rates of ventilated-pressurized garments. Annex F gives, for guidance, recommendations for choosing protective clothing.
|
Published |
1987-06 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
13.280
Radiation protection
;
13.340.10
Protective clothing
|
| ISO 8690:1988 |
Decontamination of radioactively contaminated surfaces — Method for testing and assessing the ease of decontamination |
Is designed to obtain data allowing the comparison of the ease of decontamination of different surface materials and can be used for comparative tests with any radionuclide in aqueous solution. Comparison is based on the mean residual pulse rates. In order to allow the general qualifications of a surface material as a single product, a method based on contamination by solutions containing Co-60 and Cs-137 is specified. Decontaminability data obtained are not applicable to technical systems.
|
Withdrawn |
1988-08 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
|
| ISO 8690:2020 |
Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials |
This document applies to the testing of surfaces that may become contaminated by radioactive materials.
The ease of decontamination is a property of a surface and an important criterion for selecting surface materials used in the nuclear industry, interim storage or disposal facilities from which contamination can be removed easily and rapidly without damaging the surface. The test described in this document is a rapid laboratory-based method to compare the ease of decontamination of different surface materials.
The results from the test can be one parameter to take into account when selecting surface coatings such as varnish or impervious layers such as ceramics and other surfaces. The radionuclides used in this test are those commonly found in the nuclear industry (137Cs, 134Cs and 60Co) in aqueous form. The test can also be adopted for use with other radionuclides and other chemical forms, depending on the customer requirements, if the solutions are chemically stable and do not corrode the test specimen.
The test does not measure the ease of decontamination of the surface materials in practical use, as this depends on the radionuclide(s) present, their chemical form, the duration of exposure to the contaminant and the environmental conditions amongst other factors.
The test method is not intended to describe general decontamination procedures or to assess the efficiency of decontamination procedures (see ISO 7503 series).
The test method is not suitable for use of radiochemicals if the radionuclide emit low energy gamma rays or beta particles that are readily attenuated in the surface.
|
Published |
2020-09 |
Edition : 2 |
Number of pages : 34 |
Technical Committee |
13.280
Radiation protection
|
| ISO 8690:2020/AWI Amd 1 |
Measurement of radioactivity — Gamma ray and beta emitting radionuclides — Test method to assess the ease of decontamination of surface materials — Amendment 1 |
|
Under development |
|
Edition : 2 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 9271:1992 |
Decontamination of radioactively contaminated surfaces — Testing of decontamination agents for textiles |
Gives definitions. Specifies the principle, the apparatus, the preparation of the test sample, the test agents and procedure, calculation of results, the test report and the consideration of other properties.
|
Withdrawn |
1992-02 |
Edition : 1 |
Number of pages : 17 |
Technical Committee |
13.280
Radiation protection
|
| ISO 9271:2023 |
Decontamination of radioactively contaminated surfaces — Testing of decontamination agents for textiles |
This document applies to the testing of the decontamination of textiles, which are contaminated by radioactive materials.
The test method describes the technique to assess the efficiency of decontamination agents (see ISO 7503‑1 and ISO 7503‑3).
This document applies to the testing of detergents, which may be used in aqueous solutions for the purpose of cleaning radioactively contaminated textiles.
The radionuclides used in this test are those commonly found in the nuclear industry (60Co and 137Cs or 134Cs) in aqueous form. The test can also be adapted for use with other radionuclides and other chemical forms, depending on the customer requirements, if the solutions are chemically stable and do not damage the test specimen.
The test method is not suitable if the radionuclide emits low energy gamma rays, like 55Fe, or low energy beta or alpha particles that are readily attenuated in the textile fabrics, or if the nuclide has a chemical or isotopic interaction with the detergent used in the method (e.g. tritium which could be in several chemical forms).
The test method does not apply to the testing of the ability of detergents to remove non-radioactive dirt.
|
Published |
2023-02 |
Edition : 2 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
|
| ISO 9404-1:1991 |
Enclosures for protection against ionizing radiation — Lead shielding units for 150 mm, 200 mm and 250 mm thick walls — Part 1: Chevron units of 150 mm and 200 mm thickness |
Specifies the properties of the various lead units used in the construction of basic units (bricks, posts) and functional units (aperture bricks, windows, sphere units, plugs and reducing units). Annex A is for information only.
|
Published |
1991-09 |
Edition : 1 |
Number of pages : 44 |
Technical Committee |
13.280
Radiation protection
|
| ISO 9696:1992 |
Water quality — Measurement of gross alpha activity in non-saline water — Thick source method |
The method is based on acidifying the sample to stabilize it, evaporation almost to dryness, conversion to the sulfate form and ignition at 350 °C, transfer of a portion of the residue to a planchette and counting alpha-activity in a alpha-particle detector. Covers non-volatile (at 350 °C) alpha-active radionuclides and can be extended to saline or mineralized waters, but with a reduced sensitivity. Applies to the analysis of raw and potable waters.
|
Withdrawn |
1992-11 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 9697:1992 |
Water quality — Measurement of gross beta activity in non-saline water |
The method is based on acidifying the sample to stabilize it, evaporation almost to dryness, conversion to the sulfate form and ignition at 350 °C, transfer of a portion of the residue to a planchette and counting beta-activity in a Geiger counting assembly. Covers non-volatile beta-active radionuclides with maximum beta energies higher than 0,3 MeV. Applies to the analysis of raw and potable waters.
|
Withdrawn |
1992-11 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 9697:2008 |
Water quality — Measurement of gross beta activity in non-saline water — Thick source method |
ISO 9697:2008 specifies a method for the determination of gross beta activity in non-saline waters. The method covers non-volatile radionuclides with maximum beta energies > 0,3 MeV. Measurement of very low energy beta emitters, such as 3H; 14C, 35S and 241Pu, is not included in ISO 9697:2008.
The method is applicable to the analysis of raw and potable waters.
|
Withdrawn |
2008-11 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 9697:2015 |
Water quality — Gross beta activity in non-saline water — Test method using thick source |
ISO 9697:2015 specifies a test method for the determination of gross beta activity concentration in non-saline waters. The method covers non-volatile radionuclides with maximum beta energies of approximately 0,3 MeV or higher. Measurement of low energy beta emitters (e.g. 3H, 228Ra, 210Pb, 14C, 35S, and 241Pu) and some gaseous or volatile radionuclides (e.g. radon and radioiodine) might not be included in the gross beta quantification using the test method described in ISO 9697:2015.
This test method is applicable to the analysis of raw and drinking waters. The range of application depends on the amount of total soluble salts in the water and on the performance characteristics (background count rate and counting efficiency) of the counter used. It is the laboratory's responsibility to ensure the suitability of this method for the water samples tested.
|
Withdrawn |
2015-04 |
Edition : 3 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 9697:2018 |
Water quality — Gross beta activity — Test method using thick source |
This document specifies a test method for the determination of gross beta activity concentration in non-saline waters. The method covers non-volatile radionuclides with maximum beta energies of approximately 0,3 MeV or higher. Measurement of low energy beta emitters (e.g. 3H, 228Ra, 210Pb, 14C, 35S and 241Pu) and some gaseous or volatile radionuclides (e.g. radon and radioiodine) might not be included in the gross beta quantification using the test method described in this document.
This test method is applicable to the analysis of raw and drinking waters. The range of application depends on the amount of total soluble salts in the water and on the performance characteristics (background count rate and counting efficiency) of the counter used.
It is the laboratory's responsibility to ensure the suitability of this method for the water samples tested.
|
Published |
2018-11 |
Edition : 4 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 9698:1989 |
Water quality — Determination of tritium activity concentration — Liquid scintillation counting method |
The method specified is applicable to all types of water including seawater with concentrations of up to 10 ^ 6 Bq/m ^ 3 when using 20 ml counting vials. The method is not applicable to the analysis of organically bound tritium; its determination requires an oxidative digestion.
|
Withdrawn |
1989-12 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 22017:2020 |
Water quality — Guidance for rapid radioactivity measurements in nuclear or radiological emergency situation |
This document provides guidelines for testing laboratories wanting to use rapid test methods on water samples that may be contaminated following a nuclear or radiological emergency incident. In an emergency situation, consideration should be given to:
— taking into account the specific context for the tests to be performed, e.g. a potentially high level of contamination;
— using or adjusting, when possible, radioactivity test methods implemented during routine situations to obtain a result rapidly or, for tests not performed routinely, applying specific rapid test methods previously validated by the laboratory, e.g. for 89Sr determination;
— preparing the test laboratory to measure a large number of potentially contaminated samples.
The aim of this document is to ensure decision makers have reliable results needed to take actions quickly and minimize the radiation dose to the public.
Measurements are performed in order to minimize the risk to the public by checking the quality of water supplies. For emergency situations, test results are often compared to operational intervention levels.
NOTE Operational intervention levels (OILs) are derived from IAEA Safety Standards[8] or national authorities[9].
A key element of rapid analysis can be the use of routine methods but with a reduced turnaround time. The goal of these rapid measurements is often to check for unusual radioactivity levels in the test sample, to identify the radionuclides present and their activity concentration levels and to establish compliance of the water with intervention levels[10][11][12]. It should be noted that in such circumstances, validation parameters evaluated for routine use (e.g. reproducibility, precision, etc.) may not be applicable to the modified rapid method. However, due to the circumstances arising after an emergency, the modified method may still be fit-for-purpose although uncertainties associated with the test results need to be evaluated and may increase from routine analyses.
The first steps of the analytical approach are usually screening methods based on gross alpha and gross beta test methods (adaptation of ISO 10704 and ISO 11704) and gamma spectrometry (adaptation of ISO 20042, ISO 10703 and ISO 19581). Then, if required[13], test method standards for specific radionuclides (see Clause 2) are adapted and applied (for example, 90Sr measurement according to ISO 13160) as proposed in Annex A.
This document refers to published ISO documents. When appropriate, this document also refers to national standards or other publicly available documents.
Screening techniques that can be carried out directly in the field are not part of this document.
|
Published |
2020-08 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 9698:2010 |
Water quality — Determination of tritium activity concentration — Liquid scintillation counting method |
ISO 9698:2010 specifies the conditions for the determination of tritium activity concentration in samples of environmental water or of tritiated water using liquid scintillation counting.
The choice of the analytical procedure, either with or without distillation of the water sample prior to determination, depends on the aim of the measurement and the sample characteristics.
Direct measurement of a raw water sample using liquid scintillation counting has to consider the potential presence of other beta emitter radionuclides. To avoid interference with these radionuclides when they are detected, the quantification of tritium will be performed following the sample treatment by distillation. Three distillation procedures are described.
The method is not applicable to the analysis of organically bound tritium; its determination requires additional chemical processing (such as chemical oxidation or combustion).
With suitable technical conditions, the detection limit may be as low as 1 Bq l-1. Tritium activity concentrations below 106 Bq l-1 can be determined without any sample dilution. A prior enrichment step can significantly lower the limit of detection.
|
Withdrawn |
2010-12 |
Edition : 2 |
Number of pages : 24 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 9698:2019 |
Water quality — Tritium — Test method using liquid scintillation counting |
This document specifies a method by liquid scintillation counting for the determination of tritium activity concentration in samples of marine waters, surface waters, ground waters, rain waters, drinking waters or of tritiated water ([3H]H2O) in effluents.
The method is not directly applicable to the analysis of organically bound tritium; its determination requires additional chemical processing of the sample (such as chemical oxidation or combustion).
With suitable technical conditions, the detection limit may be as low as 1 Bq·l−1. Tritium activity concentrations below 106 Bq·l−1 can be determined without any sample dilution.
|
Published |
2019-05 |
Edition : 3 |
Number of pages : 25 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 9978:1992 |
Radiation protection — Sealed radioactive sources — Leakage test methods |
Gives terms and definitions. Describes test methods by radioactive means and non-radioactive means. Tabulates threshold detection values and limiting values for different test methods.
|
Withdrawn |
1992-02 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
13.280
Radiation protection
|
| ISO 9978:2020 |
Radiation protection — Sealed sources — Leakage test methods |
This document specifies the different leakage test methods for sealed sources. It gives a comprehensive set of procedures using radioactive and non-radioactive means.
This document applies to the following situations:
— leakage testing of test sources following design classification testing in accordance with ISO 2919[1];
— production quality control testing of sealed sources;
— periodic inspections of the sealed sources performed at regular intervals, during the working life.
Annex A of this document gives guidance to the user in the choice of the most suitable method(s) according to situation and source type.
It is recognized that there can be circumstances where special tests, not described in this document, are required.
It is emphasized, however, that insofar as production, use, storage and transport of sealed radioactive sources are concerned, compliance with this document is no substitute for complying with the requirements of the relevant IAEA regulations[17] and other relevant national regulations. It is also recognized that countries can enact statutory regulations which specify exemptions for tests, according to sealed source type, design, working environment, and activity (e.g., for very low activity reference sources where the total activity is less than the leakage test limit).
|
Published |
2020-07 |
Edition : 2 |
Number of pages : 13 |
Technical Committee |
13.280
Radiation protection
|
| ISO 10648-1:1997 |
Containment enclosures — Part 1: Design principles |
|
Published |
1997-05 |
Edition : 1 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
;
71.040.10
Chemical laboratories. Laboratory equipment
|
| ISO 10648-2:1994 |
Containment enclosures — Part 2: Classification according to leak tightness and associated checking methods |
Gives a classification of containment enclosures according to leak tightness and specifies methods for checking this tightness for the following tests: manufacturing test at the factory; acceptance test at the laboratory; test before commissioning; periodical tests during operation.
|
Published |
1994-12 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
13.280
Radiation protection
;
71.040.10
Chemical laboratories. Laboratory equipment
|
| ISO 10703:1997 |
Water quality — Determination of the activity concentration of radionuclides by high resolution gamma-ray spectrometry |
|
Withdrawn |
1997-05 |
Edition : 1 |
Number of pages : 17 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 12749-2:2013 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 2: Radiological protection |
ISO 12749-2:2013 lists unambiguous terms and definitions related to radiological protection concepts in the subject field of nuclear energy. It is intended to facilitate communication and promote common understanding.
|
Withdrawn |
2013-09 |
Edition : 1 |
Number of pages : 35 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
|
| ISO 10704:2009 |
Water quality — Measurement of gross alpha and gross beta activity in non-saline water — Thin source deposit method |
ISO 10704:2009 specifies a method for the determination of gross alpha and gross beta activity in non‑saline waters for alpha- and beta‑emitting radionuclides.
The method is applicable to raw and potable waters containing a small quantity of dissolved matter. It can, after adaptation, apply to other kind of waters.
The range of application depends upon the amount of dissolved material in the water and on the performance characteristics of the measurement equipment (background count rate and counting efficiency).
|
Withdrawn |
2009-11 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 10704:2019 |
Water quality — Gross alpha and gross beta activity — Test method using thin source deposit |
This document specifies a method for the determination of gross alpha and gross beta activity concentration for alpha- and beta-emitting radionuclides. Gross alpha and gross beta activity measurement is not intended to give an absolute determination of the activity concentration of all alpha and beta emitting radionuclides in a test sample, but is a screening analysis to ensure particular reference levels of specific alpha and beta emitters have not been exceeded. This type of determination is also known as gross alpha and gross beta index. Gross alpha and gross beta analysis is not expected to be as accurate nor as precise as specific radionuclide analysis after radiochemical separations.
Maximum beta energies of approximately 0,1 MeV or higher are well measured. It is possible that low energy beta emitters can not detected (e.g. 3H, 55Fe, 241Pu) or can only be partially detected (e.g. 14C, 35S, 63Ni, 210Pb, 228Ra).
The method covers non-volatile radionuclides, since some gaseous or volatile radionuclides (e.g. radon and radioiodine) can be lost during the source preparation.
The method is applicable to test samples of drinking water, rainwater, surface and ground water as well as cooling water, industrial water, domestic and industrial wastewater after proper sampling, sample handling, and test sample preparation (filtration when necessary and taking into account the amount of dissolved material in the water).
The method described in this document is applicable in the event of an emergency situation, because the results can be obtained in less than 1 h. Detection limits reached for gross alpha and gross beta are less than 10 Bq/l and 20 Bq/l respectively. The evaporation of 10 ml sample is carried out in 20 min followed by 10 min counting with window-proportional counters.
It is the laboratory's responsibility to ensure the suitability of this test method for the water samples tested.
|
Published |
2019-02 |
Edition : 2 |
Number of pages : 20 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 11932:1996 |
Activity measurements of solid materials considered for recycling, re-use or disposal as non-radioactive waste |
Guidance and methods for activity measurements of materials to be released for recycling, re-use or disposal as non-radioactive waste arising from the operation of nuclear facilities.
|
Published |
1996-12 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
13.030.10
Solid wastes
|
| ISO 11933-1:1997 |
Components for containment enclosures — Part 1: Glove/bag ports, bungs for glove/bag ports, enclosure rings and interchangeable units |
|
Published |
1997-08 |
Edition : 1 |
Number of pages : 54 |
Technical Committee |
13.280
Radiation protection
|
| ISO 11933-2:1997 |
Components for containment enclosures — Part 2: Gloves, welded bags, gaiters for remote - handling tongs and for manipulators |
|
Published |
1997-08 |
Edition : 1 |
Number of pages : 58 |
Technical Committee |
13.280
Radiation protection
;
13.340.40
Hand and arm protection
|
| ISO 11933-3:1998 |
Components for containment enclosures — Part 3: Transfer systems such as plain doors, airlock chambers, double door transfer systems, leaktight connections for waste drums |
|
Published |
1998-11 |
Edition : 1 |
Number of pages : 43 |
Technical Committee |
13.280
Radiation protection
|
| ISO 11933-4:2001 |
Components for containment enclosures — Part 4: Ventilation and gas-cleaning systems such as filters, traps, safety and regulation valves, control and protection devices |
|
Published |
2001-05 |
Edition : 1 |
Number of pages : 80 |
Technical Committee |
13.280
Radiation protection
|
| ISO 11933-5:2001 |
Components for containment enclosures — Part 5: Penetrations for electrical and fluid circuits |
|
Published |
2001-09 |
Edition : 1 |
Number of pages : 52 |
Technical Committee |
13.280
Radiation protection
|
| ISO 11934:1997 |
X and gamma radiation — Indirect- or direct- reading capacitor-type pocket dosemeters |
|
Withdrawn |
1997-05 |
Edition : 1 |
Number of pages : 17 |
Technical Committee |
13.280
Radiation protection
|
| ISO 12749-1:2020 |
Nuclear energy — Vocabulary — Part 1: General terminology |
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.
|
Published |
2020-05 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
;
01.040.27
Energy and heat transfer engineering (Vocabularies)
;
27.120.01
Nuclear energy in general
|
| ISO 12749-2:2022 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 2: Radiological protection |
This document defines terms and definitions related to radiological protection concepts in the subject field of nuclear energy, nuclear technology and the different nuclear applications. It is intended to facilitate communication and promote common understanding.
|
Published |
2022-08 |
Edition : 2 |
Number of pages : 48 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
|
| ISO/CD 12749-3 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 3: Nuclear installations, processes and technologies |
The scope of this project supports the collection of terms, definitions, examples and notes to entry corresponding to the sub subject field nuclear installations, processes and technologies.
This is the version corresponding to the systematic review of the ISO 12749-3:2015 which scope has been changed due to the new scope of the ISO/TC85/SC5 that covers not only the nuclear fuel cycle, but also the installations, processes and technologies related to the nuclear fuel.
The project will be carried out according to the standards developed by ISO/TC37 as follows: ISO 704:2009 "Terminology work - Principles and methods", ISO 1087:2019 "Terminology work and terminology science - Vocabulary", ISO 10241-1:2011 "Terminological entries in standards - Part 1: General requirements and examples of presentation", ISO 15188:2001 "Project management guidelines for terminology standardization" and ISO 860:2007 "Terminology work - Harmonization of concepts and terms".
|
Under development |
|
Edition : 1 |
|
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
;
01.040.27
Energy and heat transfer engineering (Vocabularies)
;
27.120.01
Nuclear energy in general
|
| ISO 12749-3:2015 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 3: Nuclear fuel cycle |
ISO 12749-3:2015 lists unambiguous terms and definitions related to nuclear fuel cycle concepts in the subject field of nuclear energy, excluding reactor operations. It is intended to facilitate communication and promote common understanding.
|
Published |
2015-08 |
Edition : 1 |
Number of pages : 36 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
|
| ISO 12749-4:2015 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 4: Dosimetry for radiation processing |
ISO 12749-4:2015 lists unambiguous terms and definitions for concepts for dosimetry related to radiation processing using gamma radiation, X-radiation, or accelerated electrons. It is intended to facilitate communication and promote common understanding.
|
Published |
2015-08 |
Edition : 1 |
Number of pages : 29 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
|
| ISO 12749-5:2018 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 5: Nuclear reactors |
ISO 12749-5:2018 encompasses the collection of terms, definitions, notes and examples corresponding to nuclear reactors, excluding quantitative data. It provides the minimum essential information for each nuclear reactor concept represented by a single term. Full understanding of concepts requires background knowledge of the nuclear field. It is intended to facilitate communication and promote common understanding.
The scope of ISO 12749-5:2018 covers the whole field of nuclear reactors at a broad surface level.
|
Published |
2018-02 |
Edition : 1 |
Number of pages : 54 |
Technical Committee |
13.280
Radiation protection
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
|
| ISO 12749-6:2020 |
Nuclear energy, nuclear technologies, and radiological protection — Vocabulary — Part 6: Nuclear medicine |
This document contains the terms, definitions, notes to entry and examples corresponding to the frequently used concepts which apply to diagnostic and therapeutic nuclear medicine.
It comprises the minimum essential information for each nuclear medicine concept represented by a single term. It provides the reader with the information required to approach this multidisciplinary speciality, such as medical, radiopharmacy and medical physics point of view. It is intended to facilitate communication and promote common understanding.
|
Published |
2020-11 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
01.040.11
Health care technology (Vocabularies)
;
01.040.13
Environment. Health protection. Safety (Vocabularies)
;
11.020.20
Medical science
|
| ISO 12790-1:2001 |
Radiation protection — Performance criteria for radiobioassay — Part 1: General principles |
|
Withdrawn |
2001-12 |
Edition : 1 |
Number of pages : 31 |
Technical Committee |
13.280
Radiation protection
|
| ISO 12794:2000 |
Nuclear energy — Radiation protection — Individual thermoluminescence dosemeters for extremities and eyes |
|
Withdrawn |
2000-03 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
13.280
Radiation protection
|
| ISO/R 716:1968 |
Verification of Rockwell B and C scale hardness testing machines |
|
Withdrawn |
1968-05 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 12807:2018 |
Safe transport of radioactive materials — Leakage testing on packages |
This document specifies gas leakage test criteria and test methods for demonstrating that packages used to transport radioactive materials comply with the package containment requirements defined in the International Atomic Energy Agency (IAEA) Regulations for the Safe Transport of Radioactive Material for:
— design verification;
— fabrication verification;
— preshipment verification;
— periodic verification;
— maintenance verification.
This document describes a method for relating permissible activity release of the radioactive contents carried within a containment system to equivalent gas leakage rates under specified test conditions. This approach is called gas leakage test methodology. However, in this document it is recognized that other methodologies might be acceptable, provided that they demonstrate that any release of the radioactive contents will not exceed the regulatory requirements, and subject to agreement with the competent authority.
This document provides both overall and detailed guidance on the complex relationships between an equivalent gas leakage test and a permissible activity release rate. Whereas the overall guidance is universally agreed upon, the use of the detailed guidance shall be agreed upon with the competent authority during the Type B(U), Type B(M) or Type C packages certification process.
It should be noted that, for a given package, demonstration of compliance is not limited to a single methodology.
While this document does not require particular gas leakage test procedures, it does present minimum requirements for any test that is to be used. It is the responsibility of the package designer or consignor to estimate or determine the maximum permissible release rate of radioactivity to the environment and to select appropriate leakage test procedures that have adequate sensitivity.
This document pertains specifically to Type B(U), Type B(M) or Type C packages for which the regulatory containment requirements are specified explicitly.
|
Published |
2018-09 |
Edition : 2 |
Number of pages : 85 |
Technical Committee |
13.280
Radiation protection
;
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 13164-1:2013 |
Water quality — Radon-222 — Part 1: General principles |
ISO 13164-1:2013 gives general guidelines for sampling, packaging, and transporting of all kinds of water samples, for the measurement of the activity concentration of radon-222.
The test methods fall into two categories: a) direct measurement of the water sample without any transfer of phase (see ISO 13164‑2); b) indirect measurement involving the transfer of the radon-222 from the aqueous phase to another phase (see ISO 13164‑3).
The test methods can be applied either in the laboratory or on site.
The laboratory is responsible for ensuring the suitability of the test method for the water samples tested.
|
Published |
2013-09 |
Edition : 1 |
Number of pages : 25 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-2:2013 |
Water quality — Radon-222 — Part 2: Test method using gamma-ray spectrometry |
ISO 13164-2:2013 specifies a test method for the determination of radon-222 activity concentration in a sample of water following the measurement of its short-lived decay products by direct gamma-spectrometry of the water sample.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available gamma-ray instruments, range from a few becquerels per litre to several hundred thousand becquerels per litre for a 1 l test sample.
This test method can be used successfully with drinking water samples. The laboratory is responsible for ensuring the validity of this test method for water samples of untested matrices.
An annex gives indications on the necessary counting conditions to meet the required sensitivity for drinking water monitoring.
|
Published |
2013-09 |
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 13164-3:2013 |
Water quality — Radon-222 — Part 3: Test method using emanometry |
ISO 13164-3:2013 specifies a test method for the determination of radon-222 activity concentration in a sample of water following its transfer from the aqueous phase to the air phase by degassing and its detection. It gives recommendations for rapid measurements performed within less than 1 h.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, range from 0,1 Bq l−1 to several hundred thousand becquerels per litre for a 100 ml test sample.
This test method is used successfully with drinking water samples. The laboratory is responsible for ensuring the validity of this test method for water samples of untested matrices.
This test method can be applied on field sites or in the laboratory.
Annexes A and B give indications on the necessary counting conditions to meet the required sensitivity for drinking water monitoring
|
Published |
2013-09 |
Edition : 1 |
Number of pages : 23 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13164-4:2015 |
Water quality — Radon-222 — Part 4: Test method using two-phase liquid scintillation counting |
ISO 13164-4:2015 describes a test method for the determination of radon-222 (222Rn) activity concentration in non-saline waters by extraction and liquid scintillation counting.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, are at least above 0,5 Bq l−1 for a 10 ml test sample and a measuring time of 1 h.
This test method can be used successfully with drinking water samples and it is the responsibility of the laboratory to ensure the validity of this test method for water samples of untested matrices.
Annex A gives indication on the necessary counting conditions to meet the required detection limits for drinking water monitoring.
|
Published |
2015-06 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 148-1:2006 |
Metallic materials — Charpy pendulum impact test — Part 1: Test method |
ISO 148-1:2006 specifies the Charpy pendulum impact (V-notch and U-notch) test method for determining the energy absorbed in an impact test of metallic materials.
ISO 148-1:2006 does not address instrumented impact testing, which is specified in ISO 14556:2000.
|
Withdrawn |
2006-02 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/FDIS 13164-4 |
Water quality — Radon-222 — Part 4: Test method using two-phase liquid scintillation counting |
ISO 13164-4:2015 describes a test method for the determination of radon-222 (222Rn) activity concentration in non-saline waters by extraction and liquid scintillation counting.
The radon-222 activity concentrations, which can be measured by this test method utilizing currently available instruments, are at least above 0,5 Bq l−1 for a 10 ml test sample and a measuring time of 1 h.
This test method can be used successfully with drinking water samples and it is the responsibility of the laboratory to ensure the validity of this test method for water samples of untested matrices.
Annex A gives indication on the necessary counting conditions to meet the required detection limits for drinking water monitoring.
|
Under development |
|
Edition : 2 |
Number of pages : 16 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13166:2014 |
Water quality — Uranium isotopes — Test method using alpha-spectrometry |
ISO 13166:2014 specifies the conditions for the determination of uranium isotope activity concentration in samples of environmental water (including sea waters) using alpha-spectrometry and 232U as a yield tracer. A chemical separation is required to separate and purify uranium from a test portion of the sample.
Plutonium isotopes can interfere, if present, with detectable activities in the sample.
The detection limit for measurement of a test portion of about 500 ml is approximately 5 mBq · l−1 with a counting time of about 200 000 s.
|
Withdrawn |
2014-03 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 13166:2020 |
Water quality — Uranium isotopes — Test method using alpha-spectrometry |
This document specifies the conditions for the determination of uranium isotope activity concentration in samples of environmental water (including sea waters) using alpha-spectrometry and 232U as a yield tracer.
A chemical separation is required to separate and purify uranium from a test portion of the sample.
|
Published |
2020-08 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO/FDIS 13167 |
Water quality — Plutonium, americium, curium and neptunium — Test method using alpha spectrometry |
ISO 13167:2015 specifies a test method for measuring actinides (238Pu, 239+240Pu, 241Am, 242Cm, 243+244Cm and 237Np) in water samples by alpha spectrometry following a chemical separation.
The method can be used for any type of environmental study or monitoring.
The volume of the test portion required depends on the assumed activity of the sample and the desired detection limit.
The detection limit of the test method is 5 × 10−3 to 5 × 10−4 Bq/l for a volume of the test portion of 0,1 l to 5 l with a counting time of two to ten days.
|
Under development |
|
Edition : 2 |
Number of pages : 29 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO 13168:2015 |
Water quality — Simultaneous determination of tritium and carbon 14 activities — Test method using liquid scintillation counting |
ISO 13168:2015 describes a test method for the simultaneous measurement of tritium and carbon-14 in water samples by liquid scintillation counting of a source obtained by mixing the water sample with a hydrophilic scintillation cocktail.
This is considered a screening method because of the potential presence of interfering nuclides in the test sample.
The method can be used for any type of environmental study or monitoring.
ISO 13168:2015 is applicable to all types of waters having an activity concentration ranging from 5 Bq/l to 106 Bq/l (upper limit of the liquid scintillation counters for direct counting). For higher activity concentrations, the sample can be diluted to obtain a test sample within this range.
|
Published |
2015-07 |
Edition : 1 |
Number of pages : 16 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO/DIS 13168 |
Water quality — Simultaneous determination of tritium and carbon 14 activities — Test method using liquid scintillation counting |
|
Under development |
|
Edition : 2 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
13.060.60
Examination of physical properties of water
|
| ISO 13304-1:2013 |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 1: General principles |
The primary purpose of ISO 13304-1:2013 is to provide minimum acceptable criteria required to establish procedure of retrospective dosimetry by electron paramagnetic resonance spectroscopy and to report the results.
The second purpose is to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories.
ISO 13304-1:2013 covers the determination of absorbed dose in the measured material. It does not cover the calculation of dose to organs or to the body. It covers measurements in both biological and inanimate samples, and specifically:
based on inanimate environmental materials, usually made at X-band microwave frequencies (8 GHz to 12 GHz);
in vitro tooth enamel using concentrated enamel in a sample tube, usually employing X-band frequency, but higher frequencies are also being considered;
in vivo tooth dosimetry, currently using L-band (1 GHz to 2 GHz), but higher frequencies are also being considered;
in vitro nail dosimetry using nail clippings measured principally at X-band, but higher frequencies are also being considered;
in vivo nail dosimetry with the measurements made at X-band on the intact finger or toe;
in vitro measurements of bone, usually employing X-band frequency, but higher frequencies are also being considered.
For the biological samples, the in vitro measurements are carried out in samples after their removal from the person and under laboratory conditions, whereas the measurements in vivo may take place under field conditions.
NOTE The dose referred to in ISO 13304-1:2013 is the absorbed dose of ionizing radiation in the measured materials.
|
Withdrawn |
2013-07 |
Edition : 1 |
Number of pages : 18 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 13304-1:2020 |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 1: General principles |
The primary purpose of this document is to provide minimum acceptable criteria required to establish a procedure for retrospective dosimetry by electron paramagnetic resonance spectroscopy and to report the results.
The second purpose is to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories.
This document covers the determination of absorbed dose in the measured material. It does not cover the calculation of dose to organs or to the body. It covers measurements in both biological and inanimate samples, and specifically:
a) based on inanimate environmental materials like glass, plastics, clothing fabrics, saccharides, etc., usually made at X-band microwave frequencies (8 GHz to 12 GHz);
b) in vitro tooth enamel using concentrated enamel in a sample tube, usually employing X-band frequency, but higher frequencies are also being considered;
c) in vivo tooth dosimetry, currently using L-band (1 GHz to 2 GHz), but higher frequencies are also being considered;
d) in vitro nail dosimetry using nail clippings measured principally at X-band, but higher frequencies are also being considered;
e) in vivo nail dosimetry with the measurements made at X-band on the intact finger or toe;
f) in vitro measurements of bone, usually employing X-band frequency, but higher frequencies are also being considered.
For biological samples, in vitro measurements are carried out in samples after their removal from the person or animal and under laboratory conditions, whereas the measurements in vivo are carried out without sample removal and may take place under field conditions.
NOTE The dose referred to in this document is the absorbed dose of ionizing radiation in the measured materials.
|
Published |
2020-07 |
Edition : 2 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 13304-2:2020 |
Radiological protection — Minimum criteria for electron paramagnetic resonance (EPR) spectroscopy for retrospective dosimetry of ionizing radiation — Part 2: Ex vivo human tooth enamel dosimetry |
The purpose of this document is to provide minimum criteria required for quality assurance and quality control, evaluation of the performance and to facilitate the comparison of measurements related to absorbed dose estimation obtained in different laboratories applying ex vivo X-band EPR spectroscopy with human tooth enamel.
This document covers the determination of absorbed dose in tooth enamel (hydroxyapatite). It does not cover the calculation of dose to organs or to the body.
This document addresses:
a) responsibilities of the customer and laboratory;
b) confidentiality and ethical considerations;
c) laboratory safety requirements;
d) the measurement apparatus;
e) preparation of samples;
f) measurement of samples and EPR signal evaluation;
g) calibration of EPR dose response;
h) dose uncertainty and performance test;
i) quality assurance and control.
|
Published |
2020-07 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| ISO 14146:2000 |
Radiation protection — Criteria and performance limits for the periodic evaluation of processors of personal dosemeters for X and gamma radiation |
|
Withdrawn |
2000-06 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
13.280
Radiation protection
|
| ISO 14146:2018 |
Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services |
The quality of a supplier of a dosimetry service depends on both the characteristics of the approved (type‑tested) dosimetry system[1] and the training and experience of the staff, together with the calibration procedures and quality assurance programmes.
This document specifies the criteria and the test procedures to be used for the periodic verification of the performance of dosimetry services supplying personal and/or area dosemeters.
An area dosemeter can be a workplace dosemeter or an environmental dosemeter.
The performance evaluation can be carried out as a part of the approval procedure for a dosimetry system or as an independent check to verify that a dosimetry service fulfils specified national or international type test performance requirements under representative exposure conditions that are expected or mimic workplace fields from the radiological activities being monitored.
This document applies to personal and area dosemeters for the assessment of external photon radiation with a (fluence weighted) mean energy between 8 keV and 10 MeV, beta radiation with a (fluence weighted) mean energy between 60 keV and 1,2 MeV, and neutron radiation with a (fluence weighted) mean energy between 25,3 meV (i.e. thermal neutrons with a Maxwellian energy distribution with kT = 25,3 meV) and 200 MeV.
It covers all types of personal and area dosemeters needing laboratory processing (e.g. thermoluminescent, optically stimulated luminescence, radiophotoluminescent, track detectors or photographic-film dosemeters) and involving continuous measurements or measurements repeated regularly at fixed time intervals (e.g. several weeks, one month).
Active dosemeters (for dose measurement) may also be treated according to this document. Then, they should be treated as if they were passive (i.e. the dosimetry service reads their indicated values and reports them to the evaluation organization).
[1] If this document is applied to a dosimetry system for which no approval (pattern or type test) has been provided, then in the following text approval or type test should be read as the technical data sheet provided by the manufacturer or as the data sheet required by the regulatory authority.
|
Published |
2018-07 |
Edition : 2 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
|
| ISO/CD 14146 |
Radiological protection — Criteria and performance limits for the periodic evaluation of dosimetry services |
The quality of a supplier of a dosimetry service depends on both the characteristics of the approved (type‑tested) dosimetry system[1] and the training and experience of the staff, together with the calibration procedures and quality assurance programmes.
This document specifies the criteria and the test procedures to be used for the periodic verification of the performance of dosimetry services supplying personal and/or area dosemeters.
An area dosemeter can be a workplace dosemeter or an environmental dosemeter.
The performance evaluation can be carried out as a part of the approval procedure for a dosimetry system or as an independent check to verify that a dosimetry service fulfils specified national or international type test performance requirements under representative exposure conditions that are expected or mimic workplace fields from the radiological activities being monitored.
This document applies to personal and area dosemeters for the assessment of external photon radiation with a (fluence weighted) mean energy between 8 keV and 10 MeV, beta radiation with a (fluence weighted) mean energy between 60 keV and 1,2 MeV, and neutron radiation with a (fluence weighted) mean energy between 25,3 meV (i.e. thermal neutrons with a Maxwellian energy distribution with kT = 25,3 meV) and 200 MeV.
It covers all types of personal and area dosemeters needing laboratory processing (e.g. thermoluminescent, optically stimulated luminescence, radiophotoluminescent, track detectors or photographic-film dosemeters) and involving continuous measurements or measurements repeated regularly at fixed time intervals (e.g. several weeks, one month).
Active dosemeters (for dose measurement) may also be treated according to this document. Then, they should be treated as if they were passive (i.e. the dosimetry service reads their indicated values and reports them to the evaluation organization).
[1] If this document is applied to a dosimetry system for which no approval (pattern or type test) has been provided, then in the following text approval or type test should be read as the technical data sheet provided by the manufacturer or as the data sheet required by the regulatory authority.
|
Under development |
|
Edition : 3 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 148-1:2009 |
Metallic materials — Charpy pendulum impact test — Part 1: Test method |
ISO 148-1:2009 specifies the Charpy pendulum impact (V‑notch and U‑notch) test method for determining the energy absorbed in an impact test of metallic materials.
ISO 148-1:2009 does not apply to instrumented impact testing, which is specified in ISO 14556.
|
Withdrawn |
2009-11 |
Edition : 2 |
Number of pages : 26 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 14152:2001 |
Neutron radiation protection shielding — Design principles and considerations for the choice of appropriate materials |
This International Standard presents the general methodology governing the design of neutron radiation protection
shielding and the choice of neutron radiation protection shielding materials.
This International Standard is applicable to facilities and operations where neutron sources are located and used,
and where workers are occupationally exposed. These operations and facilities vary considerably in design and
purpose. These facilities and operations include, but are not limited to:
nuclear power plants;
research reactors;
particle accelerators and neutron generators;
fusion research facilities;
transportation packaging for radioactive materials operations;
medical treatment and research facilities and applications;
industrial applications such as use of devices for measuring and detecting moisture and density level;
space applications;
calibration facilities;
radiographic installations;
nuclear fuel cycle installations (reprocessing plants, plutonium solution handling facilities, shielded cells, waste
storage, etc.).
The criteria for the design of neutron shielding and the choice of shielding materials contained in this International
Standard should be applied to the design of neutron radiation protection shielding systems in such facilities.
|
Published |
2001-12 |
Edition : 1 |
Number of pages : 75 |
Technical Committee |
13.280
Radiation protection
|
| ISO 14152:2001/Cor 1:2002 |
Neutron radiation protection shielding — Design principles and considerations for the choice of appropriate materials — Technical Corrigendum 1 |
|
Published |
2002-05 |
Edition : 1 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 15080:2001 |
Nuclear facilities — Ventilation penetrations for shielded enclosures |
|
Published |
2001-09 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 15080:2001/Amd 1:2019 |
Nuclear facilities — Ventilation penetrations for shielded enclosures — Amendment 1 |
|
Published |
2019-05 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 15382:2002 |
Nuclear energy — Radiationprotection — Procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation |
This International Standard specifies a procedure for radiation protection monitoring in nuclear installations for external exposure to weakly penetrating radiation, especially to beta radiation and describes the procedure in radiation protection monitoring for external exposure to weakly penetrating radiation in nuclear installations. This radiation comprises beta-minus radiation, beta-plus radiation and conversion electron radiation as well as photon radiation with energies below 15 keV. This International Standard describes the procedure in radiation protection planning and monitoring as well as the measurement and analysis to be applied. It applies to regular nuclear power plant operation including maintenance, waste handling and decommissioning.
The recommendations of this International Standard may also be transferred to other nuclear fields including reprocessing, if the area-specific issues are considered. This International Standard may also be applied to radiation protection at accelerator facilities and in nuclear medicine, biology and research facilities.
|
Withdrawn |
2002-04 |
Edition : 1 |
Number of pages : 24 |
Technical Committee |
13.280
Radiation protection
|
| ISO 15382:2015 |
Radiological protection — Procedures for monitoring the dose to the lens of the eye, the skin and the extremities |
ISO 15382:2015 provides procedures for monitoring the dose to the skin, the extremities, and the lens of the eye. It gives guidance on how to decide if such dosemeters are needed and to ensure that individual monitoring is appropriate to the nature of the exposure, taking practical considerations into account. National regulations, if they exist, provide requirements that need to be followed.
ISO 15382:2015 specifies procedures for individual monitoring of radiation exposure of the skin, extremities (hands, fingers, wrists, forearms, feet and ankles), and lens of the eye in planned exposure situations. It covers practices which involve a risk of exposure to photons in the range of 8 keV to 10 MeV and electrons and positrons in the range of 60 keV to 10 MeV.
ISO 15382:2015 gives guidance for the design of a monitoring program to ensure compliance with legal individual dose limits. It refers to the appropriate operational dose quantities, and it gives guidance on the type and frequency of individual monitoring and the type and positioning of the dosemeter. Finally, different approaches to assess and analyse skin, extremity, and lens of the eye doses are given.
It is not in the scope of this International Standard to consider exposure due to alpha or neutron radiation fields.
|
Published |
2015-12 |
Edition : 2 |
Number of pages : 27 |
Technical Committee |
13.280
Radiation protection
|
| ISO 15690:2013 |
Radiological protection — Recommendations for dealing with discrepancies between personal dosimeter systems used in parallel |
ISO 15690:2013 provides recommendations for dealing with discrepancies between dosimeter systems used in parallel, in order to comply with established criteria and national regulations.
ISO 15690:2013 gives guidelines for investigating and analysing the discrepancies between the results of personal dosimetry systems, using two or more dosimeters (often one passive dosimeter and one active dosimeter), worn in parallel by the same worker.
ISO 15690:2013 identifies when the difference between measurements made by personal dosimetry systems used in parallel is considered significant and, hence, needs to be investigated.
It specifies the treatment of this difference.
In ISO 15690:2013, only the personal dose equivalent, Hp(10), from photon radiation is considered. Exposure to beta particles and neutrons might need to be taken into account when identified discrepancies are investigated.
ISO 15690:2013 applies to situations where the period of wearing can be integrated to the same period of time for both systems.
|
Published |
2013-06 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
13.280
Radiation protection
|
| ISO 16637:2016 |
Radiological protection — Monitoring and internal dosimetry for staff members exposed to medical radionuclides as unsealed sources |
ISO 16637:2016 specifies the minimum requirements for the design of professional programmes to monitor workers exposed to the risk of internal contamination via inhalation by the use of radionuclides as unsealed sources in nuclear medicine imaging and therapy departments. It establishes principles for the development of compatible goals and requirements for monitoring programmes and, when adequate, dose assessment. It presents procedures and assumptions for the risk analysis, for the monitoring programmes, and for the standardized interpretation of monitoring data.
ISO 16637:2016 addresses the following items:
a) purposes of monitoring and monitoring programmes;
b) description of the different categories of monitoring programmes;
c) quantitative criteria for conducting monitoring programmes;
d) suitable methods for monitoring and criteria for their selection;
e) information that has to be collected for the design of a monitoring programme;
f) general requirements for monitoring programmes (e.g. detection limits, tolerated uncertainties);
g) frequencies of measurements;
h) procedures for dose assessment based on reference levels for routine and special monitoring programmes;
i) assumptions for the selection of dose-critical parameter values;
j) criteria for determining the significance of individual monitoring results;
k) interpretation of workplace monitoring results;
l) uncertainties arising from dose assessments and interpretation of bioassays data;
m) reporting/documentation;
n) quality assurance.
ISO 16637:2016 does not address the following:
- monitoring and internal dosimetry for the workers exposed to laboratory use of radionuclides such as radioimmunoassay techniques;
- monitoring and internal dosimetry for the workers involved in the operation, maintenance, and servicing of PET cyclotrons;
- detailed descriptions of measuring methods and techniques;
- dosimetry for litigation cases;
- modelling for the improvement of internal dosimetry;
- the potential influence of medical treatment of the internal contamination;
- the investigation of the causes or implications of an exposure;
- dosimetry for ingestion exposures and for contaminated wounds.
|
Published |
2016-02 |
Edition : 1 |
Number of pages : 28 |
Technical Committee |
13.280
Radiation protection
|
| ISO 16639:2017 |
Surveillance of the activity concentrations of airborne radioactive substances in the workplace of nuclear facilities |
ISO 16639:2017 provides guidelines and performance criteria for sampling airborne radioactive substances in the workplace. Emphasis is on health protection of workers in the indoor environment.
ISO 16639:2017 provides best practices and performance-based criteria for the use of air sampling devices and systems, including retrospective samplers and continuous air monitors. Specifically, this document covers air sampling program objectives, design of air sampling and monitoring programs to meet program objectives, methods for air sampling and monitoring in the workplace, and quality assurance to ensure system performance toward protecting workers against unnecessary inhalation exposures.
The primary purpose of the surveillance of airborne activity concentrations in the workplace is to evaluate and mitigate inhalation hazards to workers in facilities where these can become airborne. A comprehensive surveillance program can be used to
- determine the effectiveness of administrative and engineering controls for confinement,
- measure activity concentrations of radioactive substances,
- alert workers to high activity concentrations in the air,
- aid in estimating worker intakes when bioassay methods are unavailable,
- determine signage or posting requirements for radiation protection, and
- determine appropriate protective equipment and measures.
Air sampling techniques consist of two general approaches. The first approach is retrospective sampling, in which the air is sampled, the collection medium is removed and taken to a radiation detector system and analysed for radioactive substance, and the concentration results made available at a later time. In this context, the measured air concentrations are evaluated retrospectively. The second approach is continuous real-time air monitoring so that workers can be warned that a significant release of airborne radioactivity may have just occurred. In implementing an effective air sampling program, it is important to achieve a balance between the two general approaches. The specific balance depends on hazard level of the work and the characteristics of each facility.
A special component of the second approach which can apply, if properly implemented, is the preparation of continuous air monitoring instrumentation and protocols. This enables radiation protection monitoring of personnel that have been trained and fitted with personal protective equipment (PPE) that permit pre-planned, defined, extended stay time in elevated concentrations of airborne radioactive substances. Such approaches can occur either as part of a planned re-entry of a contaminated area following an accidental loss of containment for accident assessment and recovery, or part of a project which involves systematic or routine access to radioactive substances (e.g. preparing process material containing easily aerosolized components), or handling objects such as poorly characterized waste materials that may contain radioactive contaminants that could be aerosolized when handled during repackaging. In this special case, the role of continuous air monitoring is to provide an alert to health physics personnel that the air concentrations of concern have exceeded a threshold such that the planned level of protection afforded by PPE has been or could be exceeded. This level would typically be many 10's or 100's of times higher than the derived air concentration (DAC) established for unprotected workers. The monitoring alarm or alert would therefore be designed not to be confused with the normal monitoring alarm, and the action taken in response would be similarly targeted at the specific site and personnel involved.
The air sampling strategy should be designed to minimize internal exposures and balanced with social, technical, economic, practical, and public policy considerations that are associated with the use of the radioactive substance.
A comprehensive air sampling strategy should also consider that the air sampling program is only one element of a broader radiation protection program. Therefore, individuals involved with the air sampling program should interact with personnel working in other elements of the radiation protection program, such as contamination control and internal dosimetry.
ISO 16639:2017 does not address outdoor air sampling, effluent monitoring, or radon measurements.
|
Published |
2017-01 |
Edition : 1 |
Number of pages : 32 |
Technical Committee |
13.280
Radiation protection
|
| ISO 16640:2021 |
Monitoring radioactive gases in effluents from facilities producing positron emitting radionuclides and radiopharmaceuticals |
This document focuses on monitoring the activity concentrations of radioactive gases. They allow the calculation of the activity releases, in the gaseous effluent discharge from facilities producing positron emitting radionuclides and radiopharmaceuticals. Such facilities produce short-lived radionuclides used for medical purposes or research and can release gases typically including, but not limited to 18F, 11C, 15O and 13N. These facilities include accelerators, radiopharmacies, hospitals and universities. This document provides performance‑based criteria for the design and use of air monitoring equipment including probes, transport lines, sample monitoring instruments, and gas flow measuring methods. This document also provides information on monitoring program objectives, quality assurance, development of air monitoring control action levels, system optimisation and system performance verification.
The goal of achieving an unbiased measurement is accomplished either by direct (in-line) measurement on the exhaust stream or with samples extracted from the exhaust stream (bypass), provided that the radioactive gases are well mixed in the airstream. This document sets forth performance criteria and recommendations to assist in obtaining valid measurements.
NOTE 1 The criteria and recommendations of this document are aimed at monitoring which is conducted for regulatory compliance and system control. If existing air monitoring systems were not designed according to the performance criteria and recommendations of this document, an evaluation of the performance of the system is advised. If deficiencies are discovered based on a performance evaluation, a determination of the need for a system retrofit is to be made and corrective actions adopted where practicable.
NOTE 2 The criteria and recommendations of this document apply under both normal and off‑normal operating conditions, provided that these conditions do not include production of aerosols or vapours. If the normal and/or off-normal conditions produce aerosols and vapours, then the aerosol collection principles of ISO 2889 also apply.
|
Published |
2021-01 |
Edition : 1 |
Number of pages : 54 |
Technical Committee |
13.280
Radiation protection
;
13.030.30
Special wastes
|
| ISO 16645:2016 |
Radiological protection — Medical electron accelerators — Requirements and recommendations for shielding design and evaluation |
ISO 16645:2016 is applicable to medical electron linear accelerators i.e. linear accelerators with nominal energies of the beam ranging from 4 MV to 30 MV, including particular installations such as robotic arm, helical intensity modulated radiotherapy devices and dedicated devices for intra operative radiotherapy (IORT) with electrons.
The cyclotrons and the synchrotrons used for hadrontherapy are not considered.
The radiation protection requirements and recommendations given in ISO 16645:2016 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, radiations around a linear accelerator, shielding for conventional and special devices (including shielding materials and transmission values, calculations for various treatment room configurations, duct impact on radiation protection) and the radiological monitoring (measurements).
|
Published |
2016-10 |
Edition : 1 |
Number of pages : 76 |
Technical Committee |
13.280
Radiation protection
|
| ISO/DIS 16646 |
Nuclear installations — Criteria for the design and operation of confinement and ventilation systems of tritium fusion facilities and fusion fuel handling facilities |
|
Under development |
|
Edition : 1 |
Number of pages : 77 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 16659-1:2022 |
Ventilation systems for nuclear facilities — In-situ efficiency test methods for iodine traps with solid sorbent — Part 1: General requirements |
The scope of ISO 16659 series is to provide different test methods aiming at assessing the efficiency of radioactive iodine traps in ventilation systems of nuclear facilities. The ISO 16659 series deals with iodine traps containing a solid sorbent — mainly activated and impregnated charcoal, the most common solid iodine sorbents used in the ventilation systems of nuclear facilities — as well as other sorbents for special conditions (e.g. high temperature zeolites).
The scope of this document is to provide general and common requirements for the different test methods for industrial nuclear facilities. The different methods will be described in other specific parts of ISO 16659 series. Nuclear medicine applications are excluded from the scope of ISO 16659 series.
In principle, ISO 16659 series is used mainly for filtering radioactive iodine, but other radioactive gases can also be trapped together with iodine. In such a case, some specificity may have to be adapted for these other radioactive gases in specific parts of ISO 16659 series.
This document describes the main general requirements in order to check in situ the efficiency of the iodine traps, according to test conditions that are proposed to be as reproducible as possible.
|
Published |
2022-12 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.280
Radiation protection
;
27.120.20
Nuclear power plants. Safety
|
| ISO 17099:2014 |
Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry |
ISO 17099:2014 addresses the following:
a) confidentiality of personal information for the customer and the laboratory;
b) laboratory safety requirements;
c) radiation sources, dose rates, and ranges used for establishing the calibration reference dose-effect curves allowing the dose estimation from CBMN assay yields and the minimum resolvable dose;
d) performance of blood collection, culturing, harvesting, and sample preparation for CBMN assay scoring;
e) scoring criteria;
f) conversion of micronucleus frequency in binucleated cells into an estimate of absorbed dose;
g) reporting of results;
h) quality assurance and quality control;
i) informative annexes containing examples of a questionnaire, instructions for customers, a microscope scoring data sheet, a sample report and advice on strengths and limitations of current automated systems for automated micronucleus scoring.
|
Published |
2014-11 |
Edition : 1 |
Number of pages : 31 |
Technical Committee |
13.280
Radiation protection
|
| ISO/CD 17099 |
Radiological protection — Performance criteria for laboratories using the cytokinesis block micronucleus (CBMN) assay in peripheral blood lymphocytes for biological dosimetry |
|
Under development |
|
Edition : 2 |
|
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-1:2004 |
Remote handling devices for radioactive materials — Part 1: General requirements |
ISO 17874-1:2004 describes requirements concerning devices for remote handling of radioactive materials.
|
Withdrawn |
2004-04 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-1:2010 |
Remote handling devices for radioactive materials — Part 1: General requirements |
ISO 17874-1:2010 describes requirements concerning devices for remote handling of radioactive materials. The classification of these devices (categories and different designs within a category) and the distribution in the different parts are also given.
|
Published |
2010-01 |
Edition : 2 |
Number of pages : 27 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-2:2004 |
Remote-handling devices for radioactive materials — Part 2: Mechanical master-slave manipulators |
ISO 17874-2:2004 specifies the criteria for the selection, installation and use of a mechanical master-slave manipulator, for remote handling of radiaoactive materials in a nuclear facility.
ISO 17874-2:2004 deals only with the technical aspects related to the manipulator and its interface with the nuclear facility in which it is intended to be installed.
In particular, the process apparatus and the manipulator features need to be studied in parallel in order to optimize all the functionalities of the manipulator.
However, ISO 17874-2:2004 does not cover the fundamental design criteria of the nuclear facility (e.g. the process involved, maintenance of the process equipment, intervention for other purposes).
|
Published |
2004-12 |
Edition : 1 |
Number of pages : 49 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-3:2011 |
Remote handling devices for radioactive materials — Part 3: Electrical master-slave manipulators |
ISO 17874-3:2011 specifies the main features of electrical master-slave manipulators intended to be used for nuclear applications. It outlines basic principles which relate to the design features of electrical master-slave manipulators for applications both inside and outside nuclear plant buildings.
ISO 17874-3:2011 does not address prototypes, experimental devices and obsolete types, involving variations in design which omit one or more essential features of electrical master-slave manipulators (e.g. force reflection).
|
Published |
2011-11 |
Edition : 1 |
Number of pages : 38 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-4:2006 |
Remote handling devices for radioactive materials — Part 4: Power manipulators |
ISO 17874:2006 defines the main features of power manipulators for use in ionizing radiation fields. It outlines basic principles which relate to the design and testing of power manipulators for use behind shielding walls, mainly in hot cells.
|
Published |
2006-01 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
13.280
Radiation protection
|
| ISO 17874-5:2007 |
Remote handling devices for radioactive materials — Part 5: Remote handling tongs |
The purpose of ISO 17874-5:2007 is to provide guidance for the selection, installation and use of manually-operated remote handling tongs within nuclear installations.
ISO 17874-5:2007 covers only the specific engineering aspects of manually-operated remote handling tongs and their interfaces with the nuclear facilities in which these devices are to be installed.
Specifically, ISO 17874-5:2007 does not address design options concerning aspects such as the process and general maintenance arrangements that lead to the selection of any particular type of remote handling device.
|
Published |
2007-02 |
Edition : 1 |
Number of pages : 38 |
Technical Committee |
13.280
Radiation protection
|
| ISO 22127:2019 |
Dosimetry with radiophotoluminescent glass dosimeters for dosimetry audit in MV X-ray radiotherapy |
This document specifies the dose assessment method when an RPLD is used for dosimetry audit in external high-energy X-ray beam radiotherapy.
The dosimetry for electron beams and X-ray beams of stereotactic radiotherapy, gamma‑ray of brachytherapy is not included in this version.
This document addresses RPLD handling, measurement method, conversion of measured value to dose, necessary correction coefficient, and the performance requirements for RPLD systems, including the reader.
|
Published |
2019-12 |
Edition : 1 |
Number of pages : 17 |
Technical Committee |
13.280
Radiation protection
|
| ISO/TS 18090-1:2015 |
Radiological protection — Characteristics of reference pulsed radiation — Part 1: Photon radiation |
ISO/TS 18090-1:2015 is directly applicable to pulsed X-radiation with pulse duration of 0,1 ms up to 10 s. This covers the whole range used in medical diagnostics at the time of publication. Some specifications may also be applicable for much shorter pulses; one example is the air kerma of one pulse. Such a pulse may be produced, e.g. by X-ray flash units or high-intensity femtosecond-lasers. Other specifications are not applicable for much shorter pulses; one example is the time-dependent behaviour of the air kerma rate. This may not be measurable for technical reasons as no suitable instrument is available, e.g. for pulses produced by a femtosecond-laser.
ISO/TS 18090-1:2015 specifies the characteristics of reference pulsed radiation for calibrating and testing radiation protection dosemeters and dose rate meters with respect to their response to pulsed radiation. The radiation characteristics includes the following:
a) time-dependent behaviour of the air kerma rate of the pulse;
b) time-dependent behaviour of the X-ray tube high voltage during the pulse;
c) uniformity of the air kerma rate within a cross-sectional area of the radiation beam;
d) air kerma of one radiation pulse;
e) air kerma rate of the radiation pulse;
f) repetition frequency.
ISO/TS 18090-1:2015 does not define new radiation qualities. Instead, it uses those radiation qualities specified in existing ISO and IEC standards. This part of ISO/TS 18090 gives the link between the parameters for pulsed radiation and the parameters for continuous radiation specifying the radiation qualities. It does not specify specific values or series of values for the pulsed radiation field but specifies only those limits for the relevant pulsed radiation parameters that are required for calibrating dosemeters and dose rate meters and for determining their response depending on the said parameters.
The pulse parameters with respect to the phantom-related quantities were determined using conversion coefficients according to ISO 4037 (all parts). This is possible as the radiation qualities specified in existing ISO and IEC standards are used.
A given reference pulsed X-ray facility is characterized by the parameter ranges over which the full specifications and requirements according to this part of ISO/TS 18090 are met. Therefore, not all reference pulsed X-ray facilities can produce pulses covering the same parameter ranges.
|
Published |
2015-08 |
Edition : 1 |
Number of pages : 17 |
Technical Committee |
13.280
Radiation protection
|
| ISO 18310-1:2017 |
Measurement and prediction of the ambient dose equivalent from patients receiving iodine 131 administration after thyroid ablation — Part 1: During the hospitalization |
ISO 18310-1:2017 specifies suitable methods for the measurement of ambient dose equivalent rate at a distance from the patient treated with radioiodine to ablate the thyroid. For this purpose, direct measurement of the ambient dose equivalent rate due to the inpatients using an ionization chamber (or other suitable devices) may be employed.
ISO 18310-1:2017 addresses the measurement methods, the calibration of ionization chamber and the uncertainty estimation for the measurement of the ambient dose equivalent rate of the patient treated with radioiodine to ablate the thyroid using the ionization chamber.
|
Published |
2017-01 |
Edition : 1 |
Number of pages : 22 |
Technical Committee |
13.280
Radiation protection
|
| ISO 18310-2:2021 |
Measurement and prediction of the ambient dose equivalent from patients receiving iodine 131 administration after thyroid ablation — Part 2: External effective dose of the caregivers after release from the hospital |
This document addresses the measurement methods, procedures and uncertainty estimation for the measurement, using a personal dosimeter, of the effective dose to the caregiver in the vicinity of the patient treated with radioiodine to ablate the thyroid.
The general requirements for the patient and caregiver and a guidance (see Annex A) for designated expert on instructing caregivers of discharged patients is considered to effectively measure the effective dose to the caregiver in the vicinity of the patient.
|
Published |
2021-05 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
13.280
Radiation protection
|
| ISO 18417:2017 |
Iodine charcoal sorbents for nuclear facilities — Method for defining sorption capacity index |
The scope of ISO 18417:2017 covers
- iodine sorbents for nuclear power plants, nuclear facilities, research and other nuclear reactors,
- iodine sorbents for laboratories, including nuclear medicine, and
- iodine sorbents for sampling equipment on sample lines.
ISO 18417:2017 applies to iodine sorbents manufacturers and operators in order to measure the actual performance of these sorbents and their sorption capacity for radioiodine.
ISO 18417:2017 applies to granulated and crushed iodine sorbents based on activated charcoal (hereinafter referred to as "sorbents") used for trapping gaseous radioiodine and its compounds. This document establishes the method and conditions for defining sorption capacity index in a laboratory.
|
Published |
2017-03 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
|
| ISO 19238:2004 |
Radiation protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics |
ISO 19238:2004 provides criteria for quality assurance and quality control, evaluation of the performance and the accreditation of biological dosimetry by cytogenetic service laboratories.
|
Withdrawn |
2004-08 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|