| Name |
Description |
Abstract |
Status |
Publication date |
Edition |
Number of pages |
Technical committee |
ICS |
| ISO 26261-2:2017 |
Fireworks — Category 4 — Part 2: Requirements |
ISO 26261-2:2017 specifies requirements for the construction, performance and protective packaging of Category 4 fireworks, as listed in ISO 26261‑1.
ISO 26261-2:2017 does not apply for articles containing pyrotechnic compositions that include any of the following substances:
- arsenic or arsenic compounds;
- polychlorobenzenes;
- lead or lead compounds (except for igniters);
- mercury compounds;
- white phosphorus;
- picrates or picric acid.
ISO 26261-2:2017 does not apply for theatrical pyrotechnic articles which are designed for indoor or outdoor stage use, including film and television productions or similar use.
|
Published |
2017-02 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
71.100.30
Explosives. Pyrotechnics and fireworks
|
| ISO 26261-3:2017 |
Fireworks — Category 4 — Part 3: Test methods |
ISO 26261-3:2017 specifies test methods for fireworks of Category 4.
|
Published |
2017-02 |
Edition : 1 |
Number of pages : 19 |
Technical Committee |
71.100.30
Explosives. Pyrotechnics and fireworks
|
| ISO 26261-4:2017 |
Fireworks — Category 4 — Part 4: Minimum labelling requirements and instructions for use |
ISO 26261-4:2017 specifies the minimum labelling requirements and the mandatory instructions for use for Category 4 fireworks. This document does not apply for theatrical pyrotechnic articles which are designed for indoor or outdoor stage use, including film and television productions or similar use.
|
Published |
2017-02 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
71.100.30
Explosives. Pyrotechnics and fireworks
|
| ISO 4126-1:1991 |
Safety valves — Part 1: General requirements |
Specifies requirements for safety valves irrespective of the fluid for which they are designed. Applies to valves having a flow diameter of 9 mm and above, which are for use at set pressures of 1 bar gauge (0,1 MPa) and above.
|
Withdrawn |
1991-12 |
Edition : 1 |
Number of pages : 25 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 22863-8:2021 |
Fireworks — Test methods for determination of specific chemical substances — Part 8: Arsenic content by hydride generation atomic fluorescence spectrometry |
This document specifies the test method for the determination of the arsenic content in pyrotechnic compositions by hydride generation -atomic fluorescence spectrometry
|
Published |
2021-02 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
71.100.30
Explosives. Pyrotechnics and fireworks
|
| ISO 4126-1:2013 |
Safety devices for protection against excessive pressure — Part 1: Safety valves |
ISO 4126-1:2013 specifies general requirements for safety valves irrespective of the fluid for which they are designed.
It is applicable to safety valves having a flow diameter of 4 mm and above which are for use at set pressures of 0,1 bar gauge and above. No limitation is placed on temperature.
ISO 4126-1:2013 is a product standard and is not applicable to applications of safety valves.
|
Published |
2013-07 |
Edition : 3 |
Number of pages : 14 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-1:2013/Amd 1:2016 |
Safety devices for protection against excessive pressure — Part 1: Safety valves — Amendment 1 |
|
Published |
2016-06 |
Edition : 3 |
Number of pages : 1 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-2:2003 |
Safety devices for protection against excessive pressure — Part 2: Bursting disc safety devices |
ISO 4126-2:2003 specifies the requirements for bursting disc safety devices.
ISO 4126-2:2003 includes the requirements for the design, manufacture, inspection, testing, certification, marking, and packaging.
The requirements for the application, selection and installation of bursting disc safety devices are given in ISO 4126-6.
|
Withdrawn |
2003-01 |
Edition : 1 |
Number of pages : 31 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-2:2018 |
Safety devices for protection against excessive pressure — Part 2: Bursting disc safety devices |
This document specifies the requirements for bursting disc safety devices.
It includes the requirements for the design, manufacture, inspection, testing, certification, marking, and packaging.
|
Published |
2018-12 |
Edition : 2 |
Number of pages : 21 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-3:2006 |
Safety devices for protection against excessive pressure — Part 3: Safety valves and bursting disc safety devices in combination |
ISO 4126-3:2006 specifies the requirements for a product assembled from the in-series combination of safety valves or CSPRS (controlled safety pressure relief systems) according to ISO 4126-1, ISO 4126-4 and ISO 4126-5, and bursting disc safety devices according to ISO 4126-2 installed within no more than five pipe diameters from the valve inlet. It specifies the design, application and marking requirements for such products, which are used to protect pressure vessels, piping or other enclosures from excessive pressure, and which comprise the bursting disc safety device, a safety valve or CSPRS and, where applicable, a short length of connecting pipe or spool piece. In addition, it gives a method for establishing the combination discharge factor used in sizing combinations.
|
Withdrawn |
2006-03 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-3:2020 |
Safety devices for protection against excessive pressure — Part 3: Safety valves and bursting disc safety devices in combination |
This document specifies only the requirements for a product assembled from the in-series combination of safety valves or CSPRS (controlled safety pressure relief systems) according to ISO 4126‑1, ISO 4126‑4 and ISO 4126‑5, and bursting disc safety devices, according to ISO 4126‑2, installed upstream of the valve within five pipe diameters of the valve inlet. It specifies the design, application and marking requirements for such products, composed of the bursting disc safety device, a safety valve or CSPRS and, where applicable, a connecting pipe or spool piece. In addition, it gives a method for establishing the combination discharge factor used in sizing combinations.
|
Published |
2020-09 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-4:2004 |
Safety devices for protection against excessive pressure — Part 4: Pilot-operated safety valves |
ISO 4126-4:2003 specifies general requirements for pilot operated safety valves, other than those covered in ISO 4126-1, irrespective of the fluid for which they are designed. In all cases, the operation is carried out by the fluid in the system to be protected.
ISO 4126-4:2003 is applicable to pilot operated safety valves having a valve flow diameter of 6 mm and above which are for use at set pressures of 0,1 bar gauge and above. No limitation is placed on temperature.
This is a product standard and it is not concerned with applications for pilot operated safety valves.
|
Withdrawn |
2004-02 |
Edition : 1 |
Number of pages : 26 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-4:2004/Cor 1:2007 |
Safety devices for protection against excessive pressure — Part 4: Pilot-operated safety valves — Technical Corrigendum 1 |
|
Withdrawn |
2007-08 |
Edition : 1 |
|
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-4:2013 |
Safety devices for protection against excessive pressure — Part 4: Pilot operated safety valves |
ISO 4126-4:2013 specifies general requirements for pilot operated safety valves, irrespective of the fluid for which they are designed. In all cases, the operation is carried out by the fluid in the system to be protected.
It is applicable to pilot operated safety valves having a valve flow diameter of 4 mm and above which are for use at set pressures of 0,1 bar gauge and above. No limitation is placed on temperature.
ISO 4126-4:2013 is a product standard and it is not applicable to applications of pilot operated safety valves.
|
Published |
2013-07 |
Edition : 2 |
Number of pages : 16 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 3310-1:2000 |
Test sieves — Technical requirements and testing — Part 1: Test sieves of metal wire cloth |
|
Withdrawn |
2000-07 |
Edition : 4 |
Number of pages : 15 |
Technical Committee |
19.120
Particle size analysis. Sieving
|
| ISO 4126-5:2004 |
Safety devices for protection against excessive pressure — Part 5: Controlled safety pressure relief systems (CSPRS) |
ISO 4126-5:2004 specifies the requirements for controlled safety pressure relief systems, irrespective of the fluid for which they are designed. It is applicable to main valves having a flow diameter of 6 mm and above for use at pressures of 0,1 bar (= 0,01 MPa) gauge and above. No limitation is placed on temperature.This is a product standard and is not concerned with applications.
|
Withdrawn |
2004-03 |
Edition : 1 |
Number of pages : 27 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-5:2004/Cor 1:2006 |
Safety devices for protection against excessive pressure — Part 5: Controlled safety pressure relief systems (CSPRS) — Technical Corrigendum 1 |
|
Withdrawn |
2006-10 |
Edition : 1 |
Number of pages : 1 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-5:2004/Cor 2:2007 |
Safety devices for protection against excessive pressure — Part 5: Controlled safety pressure relief systems (CSPRS) — Technical Corrigendum 2 |
|
Withdrawn |
2007-08 |
Edition : 1 |
Number of pages : 1 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-5:2013 |
Safety devices for protection against excessive pressure — Part 5: Controlled safety pressure relief systems (CSPRS) |
ISO 4126-5:2013 specifies the requirements for controlled safety pressure relief systems (CSPRS) irrespective of the fluid for which they are designed.
It is applicable for main valves having a flow diameter of 4 mm and above which are for use at pressures of 0,1 bar gauge and above. No limitation is placed on temperature.
ISO 4126-5:2013 is a product standard and is not applicable to applications.
|
Published |
2013-07 |
Edition : 2 |
Number of pages : 20 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-5:2013/Amd 1:2016 |
Safety devices for protection against excessive pressure — Part 5: Controlled safety pressure relief systems (CSPRS) — Amendment 1 |
|
Published |
2016-06 |
Edition : 2 |
Number of pages : 1 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-6:2003 |
Safety devices for protection against excessive pressure — Part 6: Application, selection and installation of bursting disc safety devices |
ISO 4126-6:2003 gives guidance on the application, selection and installation of bursting disc safety devices used to protect pressure equipment from excessive pressure and/or excessive vacuum.
|
Withdrawn |
2003-12 |
Edition : 1 |
Number of pages : 33 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-6:2014 |
Safety devices for protection against excessive pressure — Part 6: Application, selection and installation of bursting disc safety devices |
ISO 4126-6:2014 gives guidance on the application, selection and installation of bursting disc safety devices used to protect pressure equipment from excessive pressure and/or excessive vacuum.
|
Published |
2014-06 |
Edition : 2 |
Number of pages : 39 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-7:2004 |
Safety devices for protection against excessive pressure — Part 7: Common data |
ISO 4126-7:2004 contains data common to other parts of ISO 4126, thus avoiding unnecessary repetition, and is referenced in those other parts as appropriate.
|
Withdrawn |
2004-02 |
Edition : 1 |
Number of pages : 33 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-7:2004/Cor 1:2006 |
Safety devices for protection against excessive pressure — Part 7: Common data — Technical Corrigendum 1 |
|
Withdrawn |
2006-11 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-7:2013 |
Safety devices for protection against excessive pressure — Part 7: Common data |
ISO 4126-7:2013 specifies requirements for safety valves. It contains information which is common to ISO 4126-1 to ISO 4126-6 to avoid unnecessary repetition.
|
Published |
2013-07 |
Edition : 2 |
Number of pages : 33 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-7:2013/Amd 1:2016 |
Safety devices for protection against excessive pressure — Part 7: Common data — Amendment 1 |
|
Published |
2016-06 |
Edition : 2 |
Number of pages : 4 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 2855:1976 |
Radioactive materials — Packagings — Test for contents leakage and radiation leakage |
Specifies some methods for prototypes of transport packaging, but may not be considered universally applicable. The leak test ist provided for the containment system of containers and type A packaging for low specific activity liquid or powder sources. The homogeneity test refers to the outer surface of the shielding or the whole packaging. Both methods are inappropriate when the containment system is too large or of a type that they become impracticable.
|
Withdrawn |
1976-07 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
13.280
Radiation protection
|
| ISO/R 195:1961 |
Drift expanding test on copper and copper alloy tubes |
|
Withdrawn |
1961-05 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
77.040.10
Mechanical testing of metals
;
77.150.30
Copper products
|
| ISO 4126-9:2008 |
Safety devices for protection against excessive pressure — Part 9: Application and installation of safety devices excluding stand-alone bursting disc safety devices |
ISO 4126-9:2008 covers the application and installations of safety devices such as safety valves, safety valves and bursting disc safety devices in combination, pilot-operated safety valves and controlled safety pressure-relief systems for the protection of pressure equipment. ISO 4126-6 covers the selection, application and installation of bursting disc safety devices.
ISO 4126-9:2008 describes the normative requirements for applications and installations of safety devices to protect static pressure equipment. The information contained in ISO 4126-9:2008 assumes single-phase flow of the fluid discharged from the safety device. ISO 4126-10 provides guidance specific to two-phase flow conditions.
Equipment connected together in a system by piping of adequate capacity, which is free from potential blockages and does not contain any valve that can isolate any part, can be considered to be a safety system for the application of pressure relief.
ISO 4126-9:2008 does not deal with other safety devices, such as safety related monitoring, control and regulation devices and other limiting devices allowed by some national regulations.
|
Published |
2008-04 |
Edition : 1 |
Number of pages : 31 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126-10:2010 |
Safety devices for protection against excessive pressure — Part 10: Sizing of safety valves for gas/liquid two-phase flow |
ISO 4126-10:2010 specifies the sizing of safety valves for gas/liquid two-phase flow in pressurized systems such as: reactors, storage tanks, columns, heat exchangers, piping systems or transportation tanks/containers.
|
Published |
2010-10 |
Edition : 1 |
Number of pages : 45 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO/FDIS 4126-10 |
Safety devices for protection against excessive pressure — Part 10: Sizing of safety valves and bursting discs for gas/liquid two-phase flow |
|
Under development |
|
Edition : 2 |
|
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 4126:1981 |
Safety valves — General requirements |
|
Withdrawn |
1981-04 |
Edition : 2 |
Number of pages : 9 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 6718:1985 |
Bursting discs and bursting disc devices |
|
Withdrawn |
1985-09 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 6718:1991 |
Bursting discs and bursting disc devices |
Specifies requirements and 39 terms and definitions. This second edition cancels and replaces the first edition (1985). Annexes A, B, C and D are for information only.
|
Withdrawn |
1991-12 |
Edition : 2 |
Number of pages : 31 |
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 6718:1991/Cor 1:1993 |
Bursting discs and bursting disc devices — Technical Corrigendum 1 |
|
Withdrawn |
1993-09 |
Edition : 2 |
|
Technical Committee |
13.240
Protection against excessive pressure
|
| ISO 361:1975 |
Basic ionizing radiation symbol |
Specifies shape, proportions, application, restrictions on the use of the symbol (possibly accompanied by additional symbols or words). Shall be used to signify the actual or potential presence of ionizing radiation (including gamma and X-rays. alpha and beta particles, high-speed electrons, neutrons, protons and other nuclear particles, but not sound waves and other types of electromagnetic waves). Does not specify the radiation levels at which it is to be used.
|
Published |
1975-10 |
Edition : 1 |
Number of pages : 1 |
Technical Committee |
13.280
Radiation protection
;
01.080.20
Graphical symbols for use on specific equipment
|
| ISO 1677:1977 |
Sealed radioactive sources — General |
|
Withdrawn |
1977-06 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
13.280
Radiation protection
|
| ISO 1757:1980 |
Personal photographic dosemeters |
|
Withdrawn |
1980-06 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
13.280
Radiation protection
|
| ISO 1757:1996 |
Personal photographic dosemeters |
Specifies physical characteristics of personal photographic dosemeters and corresponding methods for testing. Applies to personnel photographic dosemeters having a minimum measuring range from 200 Sv to 1 Sv and which, in accordance with national regulations and ICRP recommendations, are used. Does not contain information on the calculation of doses.
|
Withdrawn |
1996-12 |
Edition : 2 |
Number of pages : 27 |
Technical Committee |
13.280
Radiation protection
|
| ISO 1758:1976 |
Direct-reading electroscope-type pocket exposure meters |
|
Withdrawn |
1976-12 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
13.280
Radiation protection
|
| ISO 1759:1976 |
Indirect-reading capacitor-type pocket exposure meters and accessory electrometers |
|
Withdrawn |
1976-12 |
Edition : 1 |
Number of pages : 2 |
Technical Committee |
13.280
Radiation protection
|
| ISO/IEC DTR 7052 |
Software engineering – Controlling frequently occurring risks during development and maintenance of custom software |
|
Under development |
|
Edition : 1 |
|
Technical Committee |
35.080
Software
|
| ISO 2889:1975 |
General principles for sampling airborne radioactive materials |
Sets forth the principles for collecting representative samples and prescribes acceptable methods and materials for gas and particle sampling (collection of the samples, and not their measurement), limited to sampling in installations where work with radioactive materials is conducted, including sampling effluent gases prior to, or at, the point of release to the atmosphere, and with the primary emphasis on the need to protect the radiation worker. Does not consider application of various collectors to specific problems.
|
Withdrawn |
1975-05 |
Edition : 1 |
Number of pages : 25 |
Technical Committee |
13.280
Radiation protection
|
| ISO 2889:2010 |
Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities |
ISO 2889:2010 sets forth performance-based criteria and recommendations for the design and use of systems for sampling of airborne radioactive materials in the effluent air from the ducts and stacks of nuclear facilities.
The requirements and recommendations of ISO 2889:2010 are aimed at sampling that is conducted for regulatory compliance and system control. If existing air-sampling systems are not designed to the performance requirements and recommendations of ISO 2889:2010, an evaluation of the performance of the system is advised. If deficiencies are discovered, a determination of whether or not a retrofit is needed and practicable is recommended.
It can be impossible to meet the requirements of ISO 2889:2010 in all conditions with a sampling system designed for normal operations only. Under off-normal conditions, the criteria or recommendations of ISO 2889:2010 still apply; but for accident conditions, special or separate accident air sampling systems can be necessary.
|
Withdrawn |
2010-03 |
Edition : 2 |
Number of pages : 103 |
Technical Committee |
13.280
Radiation protection
|
| ISO 2889:2021 |
Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities |
This document sets forth performance-based criteria and recommendations for the design and use of systems for sampling of airborne radioactive materials in the effluent air from the ducts and stacks of nuclear facilities.
The requirements and recommendations of this document are aimed at sampling that is conducted for regulatory compliance and system control. If existing air-sampling systems are not designed to the performance requirements and recommendations of this document, an evaluation of the performance of the system is advised. If deficiencies are discovered, a determination of whether or not a retrofit is needed and practicable is recommended.
It can be impossible to meet the requirements of this document in all conditions with a sampling system designed for normal operations only. Under off-normal conditions, the criteria or recommendations of this document still apply. However, for accident conditions, special accident air sampling systems or measurements can be used.
This document does not address outdoor air sampling, radon measurements, or the surveillance of airborne radioactive substances in the workplace of nuclear facilities.
NOTE Reference [1] addresses the instrumentation that is frequently used in nuclear air monitoring. Reference [5] addresses air sampling in the workplace of nuclear facilities. References [6] and [7] describe the performance characteristics of air monitors.
|
Published |
2021-08 |
Edition : 3 |
Number of pages : 115 |
Technical Committee |
13.280
Radiation protection
|
| ISO/FDIS 2889 |
Sampling airborne radioactive materials from the stacks and ducts of nuclear facilities |
This document sets forth performance-based criteria and recommendations for the design and use of systems for sampling of airborne radioactive materials in the effluent air from the ducts and stacks of nuclear facilities.
The requirements and recommendations of this document are aimed at sampling that is conducted for regulatory compliance and system control. If existing air-sampling systems are not designed to the performance requirements and recommendations of this document, an evaluation of the performance of the system is advised. If deficiencies are discovered, a determination of whether or not a retrofit is needed and practicable is recommended.
It can be impossible to meet the requirements of this document in all conditions with a sampling system designed for normal operations only. Under off-normal conditions, the criteria or recommendations of this document still apply. However, for accident conditions, special accident air sampling systems or measurements can be used.
This document does not address outdoor air sampling, radon measurements, or the surveillance of airborne radioactive substances in the workplace of nuclear facilities.
NOTE Reference [1] addresses the instrumentation that is frequently used in nuclear air monitoring. Reference [5] addresses air sampling in the workplace of nuclear facilities. References [6] and [7] describe the performance characteristics of air monitors.
|
Under development |
|
Edition : 4 |
Number of pages : 116 |
Technical Committee |
13.280
Radiation protection
|
| ISO 2919:1980 |
Sealed radioactive sources — Classification |
|
Withdrawn |
1980-05 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
13.280
Radiation protection
|
| ISO 2919:1999 |
Radiation protection — Sealed radioactive sources — General requirements and classification |
|
Withdrawn |
1999-02 |
Edition : 2 |
Number of pages : 19 |
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 2919:2012 |
Radiological protection — Sealed radioactive sources — General requirements and classification |
ISO 2919:2012 establishes a classification system for sealed radioactive sources that is based on test performance and specifies general requirements, performance tests, production tests, marking and certification. It provides a set of tests by which manufacturers of sealed radioactive sources can evaluate the safety of their products in use and users of such sources can select types which are suitable for the required application, especially where protection against the release of radioactive material, with consequent exposure to ionizing radiation, is concerned. ISO 2919:2012 can also serve as guidance to regulating authorities.
The tests fall into several groups, including, for example, exposure to abnormally high and low temperatures and a variety of mechanical tests. Each test can be applied in several degrees of severity. The criterion of pass or fail depends on leakage of the contents of the sealed radioactive source.
Although ISO 2919:2012 classifies sealed sources by a variety of tests, it does not imply that a sealed source will maintain its integrity if used continuously at the rated classification. For example, a sealed source tested for 1 h at 600 °C might, or might not, maintain its integrity if used continuously at 600 °C.
A list of the main typical applications of sealed radioactive sources, with a suggested test schedule for each application, is given in Table 3. The tests constitute minimum requirements corresponding to the applications in the broadest sense. Factors to be considered for applications in especially severe conditions are listed in 4.2.
ISO 2919:2012 makes no attempt to classify the design of sources, their method of construction or their calibration in terms of the radiation emitted. Radioactive materials inside a nuclear reactor, including sealed sources and fuel elements, are not covered by ISO 2919:2012.
|
Published |
2012-02 |
Edition : 3 |
Number of pages : 19 |
Technical Committee |
13.280
Radiation protection
|
| ISO 3925:1978 |
Unsealed radioactive substances — Identification and certification |
|
Withdrawn |
1978-05 |
Edition : 1 |
Number of pages : 1 |
Technical Committee |
13.280
Radiation protection
|
| ISO 3925:2014 |
Unsealed radioactive substances — Identification and documentation |
ISO 3925:2014 establishes the requirements for the identification and documentation of unsealed radioactive substances issued commercially by suppliers and which are intended for further handling or processing, either physical or chemical. Requirements for radiopharmaceuticals and standard sources are not covered.
|
Published |
2014-01 |
Edition : 2 |
Number of pages : 3 |
Technical Committee |
13.280
Radiation protection
|
| ISO 4071:1978 |
Exposure meters and dosimeters — General methods for testing |
|
Withdrawn |
1978-11 |
Edition : 1 |
Number of pages : 29 |
Technical Committee |
13.280
Radiation protection
|
| 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 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 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/CD 4721 |
Water quality - Strontium 90 – Test method using ICP/MS |
This standard describes a method for the measurement of Strontium-90 in water samples using inductively coupled plasma mass spectrometry (ICP-MS).
The method describes chemical separation using extraction chromatography, followed by analysis using ICP-MS.
|
Under development |
|
Edition : 1 |
|
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| 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 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/R 789:1968 |
Withdrawal of ISO/R 789-1968 |
|
Withdrawn |
1968-07 |
Edition : 1 |
Number of pages : 27 |
Technical Committee |
65.060.10
Agricultural tractors and trailed vehicles
|
| 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 12749-2:2022 |
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 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 12749-2:2013 |
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/FDIS 19238 |
Radiological protection — Performance criteria for service laboratories performing biological dosimetry by cytogenetics — The dicentric assay |
|
Under development |
|
Edition : 3 |
|
Technical Committee |
13.280
Radiation protection
;
17.240
Radiation measurements
|
| 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".
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Under development |
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Edition : 1 |
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Technical Committee |
13.280
Radiation protection
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01.040.13
Environment. Health protection. Safety (Vocabularies)
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01.040.27
Energy and heat transfer engineering (Vocabularies)
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27.120.01
Nuclear energy in general
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