| Name |
Description |
Abstract |
Status |
Publication date |
Edition |
Number of pages |
Technical committee |
ICS |
| ISO/ASTM 51607:2013 |
Practice for use of the alanine-EPR dosimetry system |
ISO/ASTM 51607:2013 covers dosimeter materials, instrumentation, and procedures for using the alanine-EPR dosimetry system for measuring the absorbed dose in the photon and electron radiation processing of materials. The system is based on electron paramagnetic resonance (EPR) spectroscopy of free radicals derived from the amino acid alanine.
The alanine dosimeter is classified as a type I dosimeter as it is affected by individual influence quantities in a welldefined way that can be expressed in terms of independent correction factors. The alanine dosimeter may be used in either a reference standard dosimetry system or in a routine dosimetry system.
ISO/ASTM 51607:2013 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ASTM E2628 for alanine dosimetry system. It is intended to be read in conjunction with ASTM E2628.
|
Published |
2013-06 |
Edition : 3 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51608:2002 |
Practice for dosimetry in an X-ray (bremsstrahlung) facility for radiation processing |
ISO/ASTM 15608 covers dosimetric procedures to be followed in facility characterization, process qualification and routine processing using X-rays (bremsstrahlung) to ensure that the entire product has been treated within an acceptable range of absorbed doses. Other procedures related to facility characterization, process qualification, and routine processing that may influence absorbed doses in the product are also discussed.
In contrast to mono-energetic gamma rays, the bremsstrahlung energy spectrum extends from low values up to the maximum energy of the electrons incident on the X-ray target. Bremsstrahlung characteristics are similar to gamma rays from radioactive isotopes.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
|
| ISO/ASTM 51608:2005 |
Practice for dosimetry in an X-ray (bremsstrahlung) facility for radiation processing |
ISO/ASTM 51608:2005 outlines the installation qualification program for an X-ray (bremsstrahlung) irradiator and the dosimetric procedures to be followed during operational qualification, performance qualification and routine processing to ensure that the entire product has been treated within a predetermined range of absorbed dose. Other procedures related to operational qualification, performance qualification and routine processing that may influence absorbed dose in the product are also discussed. Information about effective or regulatory dose limits and energy limits for X-radiation is not within the scope of ISO/ASTM 51608:2005.
|
Withdrawn |
2005-05 |
Edition : 2 |
Number of pages : 17 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51608:2015 |
Practice for dosimetry in an X-ray (bremsstrahlung) facility for radiation processing at energies between 50 keV and 7.5 MeV |
ISO/ASTM 51608:2015 outlines the dosimetric procedures to be followed during installation qualification, operational qualification, performance qualification and routine processing at an X-ray (bremsstrahlung) irradiator. Other procedures related to operational qualification, performance qualification and routine processing that may influence absorbed dose in the product are also discussed.
ISO/ASTM 51608:2015 is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM Practice 52628, "Practice for Dosimetry in Radiation Processing".
In contrast to monoenergetic gamma radiation, the X-ray energy spectrum extends from low values (about 35 keV) up to the maximum energy of the electrons incident on the X-ray target.
|
Published |
2015-03 |
Edition : 3 |
Number of pages : 16 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/DIS 4717 |
Water quality — Protactinium-231 — Test method using ICP-MS |
|
Under development |
|
Edition : 1 |
Number of pages : 18 |
Technical Committee |
17.240
Radiation measurements
;
13.060.60
Examination of physical properties of water
|
| ISO/ASTM 51631:2002 |
Practice for use of calorimetric dosimetry systems for electron beam dose measurements and dosimeter calibrations |
ISO/ASTM 51631 covers the preparation and use of semi-adiabatic calorimeters for measurement of absorbed doses in graphite, water or polystyrene when irradiated with electrons. The calorimeters are either transported by a conveyor past a scanned electron beam or are stationary in a broadened beam. It also covers the use of these calorimeters to calibrate dosimeter systems in electron beams intended for radiation processing applications.
This International Standard applies to electron beams in the energy range from 4 MeV to 12 MeV.
The absorbed dose range depends on the absorbing material and the irradiation and measurement conditions. The minimum dose is approximately 100 Gy and maximum dose is approximately 50 kGy.
The averaged absorbed dose rate range shall generally be greater than 10 Gy·s-1 , but depends on the same conditions as above.
The temperature range for use of these calorimeters depends on the thermal resistance of the materials and on the calibration range of the temperature sensor.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51631:2003 |
Practice for use of calorimetric dosimetry systems for electron beam dose measurements and dosimeter calibrations |
ISO/ASTM 51631:2003 covers the preparation and use of semi-adiabatic calorimeters for measurement of absorbed dose and routine dosimeter calibration when irradiated with electrons for radiation processing applications. The calorimeters are either transported by a conveyor past a scanned electron beam or are stationary in a broadened beam.
ISO/ASTM 51631:2003 applies to electron beams in the energy range from 1,5 to 12 MeV.
|
Withdrawn |
2003-07 |
Edition : 2 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51631:2013 |
Practice for use of calorimetric dosimetry systems for electron beam dose measurements and dosimetery system calibrations |
ISO/ASTM 51631:2013 covers the preparation and use of semiadiabatic calorimetric dosimetry systems for measurement of absorbed dose and for calibration of routine dosimetry systems when irradiated with electrons for radiation processing applications. The calorimeters are either transported by a conveyor past a scanned electron beam or are stationary in a broadened beam.
|
Withdrawn |
2013-04 |
Edition : 3 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51631:2020 |
Practice for use of calorimetric dosimetry systems for dose measurements and dosimetry system calibration in electron beams |
This practice covers the preparation and use of semiadiabatic calorimetric dosimetry systems for measurement of
absorbed dose and for calibration of routine dosimetry systems when irradiated with electrons for radiation processing applications.
The calorimeters are either transported by a conveyor past a scanned electron beam or are stationary in a broadened
beam.
This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM Practice
52628 for a calorimetric dosimetry system. It is intended to be read in conjunction with ISO/ASTM Practice 52628.
The calorimeters described in this practice are classified as Type II dosimeters on the basis of the complex effect of influence quantities. See ISO/ASTM Practice 52628.
This practice applies to electron beams in the energy range from 1.5 to 12 MeV.
The absorbed dose range depends on the calorimetric absorbing material and the irradiation and measurement conditions. Minimum dose is approximately 100 Gy and maximum dose is approximately 50 kGy.
The average absorbed-dose rate range shall generally be greater than 10 Gy·s-1.
The temperature range for use of these calorimetric dosimetry systems depends on the thermal resistance of the calorimetric materials, on the calibration range of the temperature sensor, and on the sensitivity of the measurement device.
This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
|
Published |
2020-02 |
Edition : 4 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51649:2002 |
Practice for dosimetry in an electron-beam facility for radiation processing at energies between 300 keV and 25 MeV |
ISO/ASTM 51649 covers dosimetric procedures to be followed in facility characterization, process qualification and routine processing using electron beam radiation in order to ensure that the entire product has been treated with an acceptable range of absorbed doses. Other procedures related to facility characterization (including equipment documentation), process qualification and routine product processing that may influence and may be used to monitor absorbed dose in the product are also discussed.
The electron energy range covered by this International Standard is between 300 keV and 25 MeV, although other energy levels are discussed.
Dosimetry is only one component of a total quality assurance programme for an irradiation facility. Other controls besides dosimetry may be required for specific applications such as medical device sterilization and food preservation.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 20 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51649:2005 |
Practice for dosimetry in an electron beam facility for radiation processing at energies between 300 keV and 25 MeV |
ISO/ASTM 51649:2005 covers dosimetric procedures to be followed in Installation Qualification, Operational Qualification and Performance Qualifications (IQ, OQ, PQ), and routine processing at electron beam facilities to ensure that the product has been treated with an acceptable range of absorbed doses. Other procedures related to IQ, OQ, PQ, and routine product processing that may influence absorbed dose in the product are also discussed.
|
Withdrawn |
2005-05 |
Edition : 2 |
Number of pages : 30 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 16495:2013 |
Packaging — Transport packaging for dangerous goods — Test methods |
ISO 16495:2013 specifies the information needed for the design type testing of packaging, Intermediate Bulk Containers ( IBCs) and large packaging intended for use in the transport of dangerous goods.
|
Withdrawn |
2013-08 |
Edition : 1 |
Number of pages : 52 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO/ASTM 51649:2015 |
Practice for dosimetry in an electron beam facility for radiation processing at energies between 300 keV and 25 MeV |
ISO/ASTM 51649:2015 outlines dosimetric procedures to be followed in installation qualification (IQ), operational qualification (OQ) and performance qualifications (PQ), and routine processing at electron beam facilities.
The electron beam energy range covered in this practice is between 300 keV and 25 MeV, although there are some discussions for other energies.
Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications. Other measures besides dosimetry may be required for specific applications such as health care product sterilization and food preservation.
ISO/ASTM 51649:2015 is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ISO/ASTM 52628, "Practice for Dosimetry in Radiation Processing".
|
Published |
2015-03 |
Edition : 3 |
Number of pages : 35 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51650:2002 |
Practice for use of a cellulose triacetate dosimetry system |
ISO 51650 covers the preparation, handling, testing and procedures for the use of cellulose acetate dosimetry systems, and the spectrometric, densitometric or photometric read-out equipment for measuring absorbed doses in materials irradiated by photons and electrons in terms of absorbed dose in water.
Cellulose acetate dosimeter refers to untinted and tinted cellulose triacetate (CTA) or cellulose diacetate (CDA) film dosimeter.
This practice applies to cellulose acetate film dosimeters that can be used within part or all of the specified ranges as follows:
the absorbed dose range for untinted CTA is 5 times 103 Gy to 3 times 10 5 Gy for photons and electrons;
the absorbed dose range for tinted CDA is 1 times 104 Gy to 1 times 10 6 Gy for photons and electrons;
the absorbed dose rate for both CTAand CDA is from 0,03 to 4 times 1010 Gy s -1;
the radiation energy range for photons is from 0,1 MeV to 50 MeV;
the radiation energy range for electrons is from 0,2 MeV to 50 MeV;
the irradiation temperature range is from - 10 °C to 70 °C.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51650:2005 |
Practice for use of a cellulose triacetate dosimetry system |
ISO/ASTM 51650:2005 covers procedures for using the cellulose triacetate (CTA) dosimetry system for measuring absorbed dose and dose profile in materials irradiated by electrons and photons in terms of absorbed dose to water. The CTA dosimeter is a routine dosimeter especially useful for measurement of dose distribution.
|
Withdrawn |
2005-05 |
Edition : 2 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51650:2013 |
Practice for use of a cellulose triacetate dosimetry system |
ISO/ASTM 51650:2013 is a practice for using a cellulose triacetate (CTA) dosimetry system to measure absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. The CTA dosimetry system is classified as a routine dosimetry system.
The CTA dosimeter is classified as a type II dosimeter on the basis of the complex effect of influence quantities on its response.
ISO/ASTM 51650:2013 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ASTM E2628 for a CTA dosimetry system. It is intended to be read in conjunction with ASTM E2628.
|
Published |
2013-06 |
Edition : 3 |
Number of pages : 6 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51702:2002 |
Practice for dosimetry in a gamma irradiation facility for radiation processing |
ISO/ASTM 15702 outlines dosimetric procedures to be followed in irradiator characterization, process qualification, and routine processing in a gamma irradiation facility. These procedures ensure that all product processed with ionizing radiation from isotopic gamma sources receive absorbed doses within a predetermined range. Other procedures related to irradiator characterization, process qualification and routine processing that may influence absorbed doses in the product are also discussed.
Dosimetry is one component of a total quality assurance programme for an irradiation facility. Other controls besides dosimetry may be required for specific applications such as medical device sterilization and food preservation.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51702:2004 |
Practice for dosimetry in a gamma irradiation facility for radiation processing |
ISO/ASTM 51702:2004 outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance qualification, and routine processing in facilities that process product with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to installation qualification, operational qualification, performance qualification, and routine processing that may influence absorbed dose in the product are also discussed.
Information about effective or regulatory absorbed-dose limits is not within the scope of ISO/ASTM 51702:2004. ISO/ASTM 51702:2004 does not provide guidance in the selection and calibration of dosimetry systems, thte interpretation of measured absorbed dose in the product or the use of specific dosimetry systems.
ISO/ASTM 51702:2004 does not purport to address all of the safety concerns, if any, associated with its use.
|
Withdrawn |
2004-08 |
Edition : 2 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 8425:1987 |
Determination of plutonium in pure plutonium nitrate solutions — Gravimetric method |
Specifies a method for determining plutonium in pure plutonium nitrate solutions and reference solutions, containing between 100 and 300 g of plutonium per litre, in a nitric acid medium. The principle of the method, interferences, reagents, apparatus, procedure and expression of results are described.
|
Withdrawn |
1987-03 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO/ASTM 51702:2013 |
Practice for dosimetry in a gamma facility for radiation processing |
ISO/ASTM 51702:2013 outlines the installation qualification program for an irradiator and the dosimetric procedures to be followed during operational qualification, performance qualification, and routine processing in facilities that process products with ionizing radiation from radionuclide gamma sources to ensure that product has been treated within a predetermined range of absorbed dose. Other procedures related to operational qualification, performance qualification, and routine processing that may influence absorbed dose in the product are also discussed.
NOTE 1 — Dosimetry is only one component of a total quality assurance program for adherence to good manufacturing practices used in radiation processing applications.
NOTE 2 — ISO/ASTM Practices 51818 and 51649 describe dosimetric procedures for low and high enery electron beam facilities for radiation processing and ISO/ASTM Practice 51608 describes procedures for X-ray (bremsstrahlung) facilities for radiation processing.
|
Published |
2013-04 |
Edition : 3 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51707:2002 |
Guide for estimating uncertainties in dosimetry for radiation processing |
ISO/ASTM 51707 defines possible sources of error in dosimetry performed in gamma, X-ray (bremsstrahlung) and electron irradiation facilities and offers procedures for estimating the resulting magnitude of the uncertainties in the measurement results. Basic concepts of measurement, estimate of the measured value of a quantity, 'true' value, error and uncertainty are defined and discussed. Components of uncertainty are discussed and methods are given for evaluating and estimating their values. How these contribute to the standard uncertainty in the reported values of absorbed doses are considered and methods are given for calculating the combined standard uncertainty and an estimate of overall (expanded) uncertainty. The methodology for evaluating components of uncertainty follows ISO procedures. The traditional concepts of precision and bias are not used. Examples are given in five annexes.
This International Standard assumes a working knowledge of statistics and several statistical texts are included in the references.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 21 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51707:2005 |
Guide for estimating uncertainties in dosimetry for radiation processing |
ISO/ASTM 51707:2005 defines possible sources of uncertainty in dosimetry performed in gamma, X-ray (bremsstrahlung), and electron irradiation facilities and offers procedures for estimating the resulting magnitude of the uncertainties in the measurement of absorbed dose using a dosimetry system.
|
Withdrawn |
2005-05 |
Edition : 2 |
Number of pages : 24 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51707:2015 |
Guide for estimation of measurement uncertainty in dosimetry for radiation processing |
ISO/ASTM 51707:2015 provides guidance on the use of concepts described in the JCGM Evaluation of Measurement Data ? Guide to the Expression of Uncertainty in Measurement (GUM) to estimate the uncertainties in the measurement of absorbed dose in radiation processing.
Methods are given for identifying, evaluating and estimating the components of measurement uncertainty associated with the use of dosimetry systems and for calculating combined standard measurement uncertainty and expanded (overall) uncertainty of dose measurements based on the GUM methodology.
Examples are given on how to develop a measurement uncertainty budget and a statement of uncertainty.
ISO/ASTM 51707:2015 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and provides guidance for achieving compliance with the requirements of ISO/ASTM 52628 related to the evaluation and documentation of the uncertainties associated with measurements made with a dosimetry system. It is intended to be read in conjunction with ISO/ASTM 52628, ISO/ASTM 51261 and ISO/ASTM 52701.
|
Published |
2015-03 |
Edition : 3 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51818:2002 |
Practice for dosimetry in an electron-beam facility for radiation processing at energies between 80 keV and 300 keV |
ISO/ASTM 51818 covers dosimetric procedures to be followed in order to determine the performance of low energy (300 keV or less) single-gap electron beam radiation processing facilities. Other practices and procedures related to facility characterization, product qualification and routine processing are also discussed.
The electron energy range covered in this International Standard is from 80 keV to 300 keV. Such electron beams can be generated by single-gap self-contained thermal filament or plasma source accelerators.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51818:2009 |
Practice for dosimetry in an electron beam facility for radiation processing at energies between 80 and 300 keV |
ISO 51818:20090 applies to dosimetric procedures to determine the performance of low-energy (300 keV or less) single-gap electron-beam radiation processing facilities.
Other practices and procedures related to facility characterization, process qualification and routine processing are also discussed.
The electron-energy range covered in ISO 51538:2009 is from 80 keV to 300 keV. Such electron beams can be generated by single-gap self-contained thermal filament or plasma-source accelerators.
|
Withdrawn |
2009-06 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 8300:2013 |
Nuclear fuel technology — Determination of plutonium content in plutonium dioxide of nuclear grade quality — Gravimetric method |
ISO 8300:2013 specifies a precise and accurate gravimetric method for determining the plutonium content in plutonium dioxide (PuO2) of nuclear grade quality, containing a mass fraction of less than 0,65 % of non-volatile impurities.
The method is used to cross-check accountancy analyses of plutonium dioxide.
|
Published |
2013-12 |
Edition : 2 |
Number of pages : 6 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO/ASTM 51818:2013 |
Practice for dosimetry in an electron beam facility for radiation processing at energies between 80 and 300 keV |
ISO/ASTM 51818:2013 covers dosimetric procedures to be followed in installation qualification, operational qualification and performance qualification (IQ, OQ, PQ), and routine processing at electron beam facilities to ensure that the product has been treated with an acceptable range of absorbed doses. Other procedures related to IQ, OQ, PQ, and routine product processing that may influence absorbed dose in the product are also discussed.
The electron beam energy range covered in ISO/ASTM 51818:2013 is between 80 and 300 keV, generally referred to as low energy. Dosimetry is only one component of a total quality assurance program for an irradiation facility. Other measures may be required for specific applications such as medical device sterilization and food preservation.
ISO/ASTM 51818:2013 is one of a set of standards that provides recommendations for properly implementing and utilizing dosimetry in radiation processing. It is intended to be read in conjunction with ASTM E2232.
|
Withdrawn |
2013-06 |
Edition : 3 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51818:2020 |
Practice for dosimetry in an electron beam facility for radiation processing at energies between 80 and 300 keV |
This practice covers dosimetric procedures to be followed in installation qualification, operational qualification and
performance qualification (IQ, OQ, PQ), and routine processing at electron beam facilities to ensure that the product has been treated with an acceptable range of absorbed doses. Other procedures related to IQ, OQ, PQ, and routine product processing that may influence absorbed dose in the product are also discussed.
The electron beam energy range covered in this practice is between 80 and 300 keV, generally referred to as low energy.
Dosimetry is only one component of a total quality assurance program for an irradiation facility. Other measures may be required for specific applications such as medical device sterilization and food preservation.
Other specific ISO and ASTM standards exist for the irradiation of food and the radiation sterilization of health care products. For the radiation sterilization of health care products, see ISO 11137-1. In those areas covered by ISO 11137-1, that standard takes precedence. For food irradiation, see ISO 14470. Information about effective or regulatory dose limits for food products is not within the scope of this practice (see ASTM F1355 and F1356).
This document is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628. It is intended to be read in conjunction with ISO/ASTM 52628.
This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
|
Published |
2020-06 |
Edition : 4 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51900:2002 |
Guide for dosimetry in radiation research on food and agricultural products |
ISO/ASTM 15900 covers the minimum requirements for dosimetry and absorbed-dose validation needed to conduct research on the irradiation of food and agricultural products. Such research includes establishment of the quantitative relationship between the absorbed dose and the relevant effects in these products. This International Standard also describes the overall need for dosimetry in such research, and in the reporting of results.
ISO/ASTM 15900 is intended for use by research scientists in the food and agricultural communities and not just scientists conducting irradiation research. It therefore includes more tutorial information than most other ASTM and ISO/ASTM dosimetry standards for radiation processing.
It is in no way intended to limit the flexibility of the experimenter in the experimental design. However, the radiation source and experimental set-up should be chosen such that the results of the experiment will be beneficial and understandable to other scientists, regulatory agencies, and the food and agricultural communities. This International Standard covers research conducted using the following types of ionizing radiation: gamma rays, bremsstrahlung X-rays and electron beams but does not include other aspects of radiation processing research, such as planning of the experimental design.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
|
| ISO/ASTM 51900:2009 |
Guide for dosimetry in radiation research on food and agricultural products |
ISO 51900:2009 applies to the minimum requirements for dosimetry needed to conduct research on the effect of radiation on food and agricultural products. Such research includes establishment of the quantitative relationship between absorbed dose and the relevant effects in these products. ISO 51900:2009 also describes the overall requirement for dosimetry in such research, and in reporting of the results. It is necessary that dosimetry be considered as an integral part of the experiment.
ISO 51900:2009 applies to research conducted using the following types of ionizing radiation: gamma radiation, X-ray (bremsstrahlung), and electron beams. The purpose of ISO 51900:2009 is to ensure that the radiation source and experimental methodology are chosen such that the results of the experiment will be useful and understandable to other scientists and regulatory agencies.
ISO 51900:2009 describes dosimetry requirements for establishing the experimental method and for routine experiments; however, ISO 51900:2009 is not intended to limit the flexibility of the experimenter in the determination of the experimental methodology. ISO 51900:2009 includes tutorial information in the form of notes.
ISO 51900:2009 does not include dosimetry requirements for installation qualification or operational qualification of the irradiation facility.
|
Withdrawn |
2009-06 |
Edition : 2 |
Number of pages : 12 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
|
| ISO/ASTM 51956:2005 |
Practice for use of thermoluminescence dosimetry (TLD) systems for radiation processing |
ISO/ASTM 51956:2005 covers procedures for the use of thermoluminescence dosimeters (TLDs) to determine the absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. It covers systems that permit absorbed dose measurements under the following conditions: the absorbed-dose range is from 1 Gy to 100 kGy; the absorbed-dose rate is between 1 x 10-2 and 1 x 1010 Gy s-1; the radiation energy range for photons and electrons is from 0,1 to 50 MeV. Absorbed dose and absorbed-dose rate measurements in materials subjected to neutron irradiation are not covered.
|
Withdrawn |
2005-05 |
Edition : 2 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 51900:2023 |
Guidance for dosimetry for radiation research |
ISO 51900:2009 applies to the minimum requirements for dosimetry needed to conduct research on the effect of radiation on food and agricultural products. Such research includes establishment of the quantitative relationship between absorbed dose and the relevant effects in these products. ISO 51900:2009 also describes the overall requirement for dosimetry in such research, and in reporting of the results. It is necessary that dosimetry be considered as an integral part of the experiment.
ISO 51900:2009 applies to research conducted using the following types of ionizing radiation: gamma radiation, X-ray (bremsstrahlung), and electron beams. The purpose of ISO 51900:2009 is to ensure that the radiation source and experimental methodology are chosen such that the results of the experiment will be useful and understandable to other scientists and regulatory agencies.
ISO 51900:2009 describes dosimetry requirements for establishing the experimental method and for routine experiments; however, ISO 51900:2009 is not intended to limit the flexibility of the experimenter in the determination of the experimental methodology. ISO 51900:2009 includes tutorial information in the form of notes.
ISO 51900:2009 does not include dosimetry requirements for installation qualification or operational qualification of the irradiation facility.
|
Published |
2023-04 |
Edition : 3 |
Number of pages : 9 |
Technical Committee |
17.240
Radiation measurements
;
67.020
Processes in the food industry
|
| ISO/ASTM 51939:2002 |
Practice for blood irradiation dosimetry |
ISO/ASTM 51939 outlines irradiator installation qualification and dosimetric procedures to be followed in the irradiation of blood and blood products by the blood-banking community. If followed, these procedures will help to ensure that the products processed with ionizing radiation from gamma, bremsstrahlung X-rays or electron sources receive absorbed doses within a predetermined range.
ISO/ASTM 51939 covers dosimetry for the irradiation of blood for the following types of irradiators: self-contained dry-storage 137Cs or 60Co irradiators (free-standing irradiators), tele-therapy units, self-contained bremsstrahlung X-ray units and electron accelerators. The absorbed dose range for blood irradiation is typically 15 Gy to 50 Gy.
This International Standard also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the product has been irradiated. It is intended for use by technically and non-technically oriented people and, therefore, contains more tutorial information than many other ISO/ASTM dosimetry standards.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
11.020
Medical sciences and health care facilities in general
;
17.240
Radiation measurements
|
| ISO/ASTM 51939:2005 |
Practice for blood irradiation dosimetry |
ISO/ASTM 51939:2005 outlines irradiator installation qualification, operational qualification, performance qualification, and routine product processing dosimetric procedures to be followed in the irradiation of blood and blood components by the blood-banking community. If followed, these procedures will help to ensure that the products processed with ionizing radiation from gamma, X-rays (bremsstrahlung), or electron sources receive absorbed doses within a predetermined range.
ISO/ASTM 51939:2005 also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the product has been irradiated.
|
Withdrawn |
2005-05 |
Edition : 2 |
Number of pages : 13 |
Technical Committee |
11.020
Medical sciences and health care facilities in general
;
17.240
Radiation measurements
|
| ISO/ASTM 51939:2013 |
Practice for blood irradiation dosimetry |
ISO/ASTM 51939:2013 outlines irradiator installation qualification, operational qualification, performance qualification and routine product processing dosimetric procedures to be followed in the irradiation of blood and blood components by the blood-banking community. If followed, these procedures will help to ensure that the products processed with ionizing radiation from gamma, X-radiation (bremsstrahlung), or electron sources receive absorbed doses within a predetermined range. ISO/ASTM 51939:2013 covers dosimetry for the irradiation of blood for these types of irradiators: self-contained irradiators (free-standing irradiators) utilizing 137Cs, 60Co or X-radiation (bremsstrahlung), teletherapy units, and electron accelerators. ISO/ASTM 51939:2013 also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the product has been irradiated.
|
Withdrawn |
2013-10 |
Edition : 3 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
11.020.99
Other standards related to health care in general
|
| ISO/ASTM 51939:2017 |
Practice for blood irradiation dosimetry |
1.1 This practice outlines the irradiator installation qualifi-cation program and the dosimetric procedures to be followed during operational qualification and performance qualification of the irradiator. Procedures for the routine radiation process-ing of blood product (blood and blood components) are also given. If followed, these procedures will help ensure that blood product exposed to gamma radiation or X-radiation (bremsstrahlung) will receive absorbed doses with a specified range.
1.2 This practice covers dosimetry for the irradiation of blood product for self-contained irradiators (free-standing irradiators) utilizing radionuclides such as 137Cs and 60Co, or X-radiation (bremsstrahlung). The absorbed dose range for blood irradiation is typically 15 Gy to 50 Gy.
1.3 The photon energy range of X-radiation used for blood irradiation is typically from 40 keV to 300 keV.
1.4 This practice also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the product has been irradiated (see ISO/ASTM Guide 51539).
1.5 ISO 51939:2017 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing and describes a means of achieving compliance with the requirements of ISO/ASTM Practice 52628 for dosimetry performed for blood irradiation. It is intended to be read in conjunction with ISO/ASTM Practice 52628.
1.6 ISO 51939:2017 does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appro-priate safety and health practices and to determine the applicability or regulatory limitations prior to use.
|
Published |
2017-02 |
Edition : 4 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
;
11.020.99
Other standards related to health care in general
|
| ISO/R 203:1961 |
Interrupted creep testing of steel at elevated temperatures (load and temperature interrupted) |
|
Withdrawn |
1961-06 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO/ASTM 51940:2002 |
Guide for dosimetry for irradiation of insects for sterile release programs |
ISO/ASTM 51940 outlines dosimetric procedures to be followed for the radiation sterilization of live insects for use in pest management programmes. The primary use of irradiated, reproductively sterile insects is in the Sterile Insect Technique, where large numbers of sterile insects are released into the field to mate with and thus control pest populations of the same species. A secondary use of irradiated insects is as benign hosts for rearing insect parasitoids. If followed, the procedures outlined in this International Standard will help to ensure that insects processed with ionizing radiation from gamma, electron or X-ray sources receive absorbed doses within a predetermined range.
ISO/ASTM 51940 covers dosimetry in the irradiation of insects for these types of irradiators: self-contained dry-storage 137Cs or 60Co irradiators, larger-scale gamma irradiators and electron accelerators. The absorbed dose for insect sterilization is typically within the range of 20 Gy to 600 Gy.
This International Standard specifically refers, throughout the text, to reproductive sterilization of insects. It is equally applicable to radiation sterilization of invertebrates from other taxa (for example, Acarina, Gastropoda) and to irradiation of live insects or other invertebrates for other purposes (e.g., inducing mutations), presuming the absorbed dose is within the range specified above.
It also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the insects have been irradiated.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
07.080
Biology. Botany. Zoology
;
17.240
Radiation measurements
|
| ISO/ASTM 51940:2004 |
Guide for dosimetry for sterile insects release programs |
ISO/ASTM 51940:2004 outlines dosimetric procedures to be followed for the radiation sterilization of live insects for use in pest management programs. The procedures outlined in ISO/ASTM 51940:2004 will help ensure that insects processed with ionizing radiation from gamma, electron, or X-ray sources receive absorbed doses within a predetermined range. Information on effective dose ranges for specific applications of insect sterilization, or on methodology for determining effective dose ranges, is not within the scope of ISO/ASTM 51940:2004.
ISO/ASTM 51940:2004 covers dosimetry in the irradiation of insects for these types of irradiators: self-contained dry-storage 137Cs or 60Co irradiators, large-scale gamma irradiators, and electron accelerators. The absorbed dose for insect sterilization is typically within the range of 20 Gy to 600 Gy.
ISO/ASTM 51940:2004 refers, throughout the text, specifically to reproductive sterilization of insects. It is equally applicable to radiation sterilization of invertebrates from other taxa (for example, Acarina, Gastropoda) and to irradiation of live insects or other invertebrates for other purposes (for example, inducing mutations), provided the absorbed dose is within the range specified.
ISO/ASTM 51940:2004 also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the insects have been irradiated.
ISO/ASTM 51940:2004 does not purport to address all of the safety concerns, if any, associated with its use.
|
Withdrawn |
2004-08 |
Edition : 2 |
Number of pages : 12 |
Technical Committee |
07.080
Biology. Botany. Zoology
;
17.240
Radiation measurements
|
| ISO/ASTM 51940:2013 |
Guide for dosimetry for sterile insects release programs |
ISO/ASTM 51940:2013 outlines dosimetric procedures to be followed for the radiation-induced reproductive sterilization of live insects for use in pest management programs. The primary use of such insects is in the Sterile Insect Technique, where large numbers of reproductively sterile insects are released into the field to mate with and thus control pest populations of the same species. A secondary use of sterile insects is as benign hosts for rearing insect parasitoids. The procedures outlined in this guide will help ensure that insects processed with ionizing radiation from gamma, electron, or X-ray sources receive absorbed doses within a predetermined range. Information on effective dose ranges for specific applications of insect sterilization, or on methodology for determining effective dose ranges, is not within the scope of this guide.
NOTE 1 — Dosimetry is only one component of a total quality assurance program to ensure that irradiated insects are adequately sterilized and fully competitive or otherwise suitable for their intended purpose.
|
Withdrawn |
2013-04 |
Edition : 3 |
Number of pages : 12 |
Technical Committee |
07.080
Biology. Botany. Zoology
;
17.240
Radiation measurements
|
| ISO/ASTM 51940:2022 |
Guidance for dosimetry for sterile insects release programs |
1.1 This document outlines dosimetric procedures to be followed for the radiation-induced reproductive sterilization of live insects for use in pest management programs. The primary use of such insects is in the Sterile Insect Technique, where large numbers of reproductively sterile insects are released into the field to mate with and thus control pest populations of the same species. A secondary use of sterile insects is as benign hosts for rearing insect parasitoids. A third use is for testing detection traps for fruit flies and moths, and testing mating disruption products for moths. The procedures outlined in this document will help ensure that insects processed with ionizing radiation from gamma, electron, or X-ray sources receive absorbed doses within a predetermined range. Information on effective dose ranges for specific applications of insect sterilization, or on methodology for determining effective dose ranges, is not within the scope of this document.
NOTE 1—Dosimetry is only one component of a total quality assurance program to ensure that irradiated insects are adequately sterilized and fully competitive or otherwise suitable for their intended purpose.
1.2 This document provides information on dosimetry for the irradiation of insects for these types of irradiators: selfcontained dry-storage 137Cs or 60Co irradiators, self-contained low-energy X-ray irradiators (maximum processing energies from 150 keV to 300 keV), large-scale gamma irradiators, and electron accelerators (electron and X-ray modes).
NOTE 2—Additional, detailed information on dosimetric procedures to be followed in installation qualification, operational qualification, performance qualification, and routine product processing can be found in ISO/ASTM Practices 51608 (X-ray [bremsstrahlung] facilities processing at energies over 300 keV), 51649 (electron beam facilities), 51702 (large-scale gamma facilities), and 52116 (self-contained dry-storage gamma facilities), and in Ref (1)2 (self-contained X-ray facilities).
1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard except for the non-SI units of minute (min) hour (h) and day (d). These non-SI units are accepted for use within the SI system.
1.4 This document is one of a set of standards that provides recommendations for properly implementing and utilizing radiation processing. It is intended to be read in conjunction with ISO/ASTM Practice 52628.
1.5 The absorbed dose for insect sterilization is typically within the range of 20 Gy to 600 Gy.
1.6 This document refers, throughout the text, specifically to reproductive sterilization of insects. It is equally applicable to radiation sterilization of invertebrates from other taxa (for example, Acarina, Gastropoda) and to irradiation of live insects or other invertebrates for other purposes (for example, inducing mutations), provided the absorbed dose is within the range specified in 1.5.
1.7 This document also covers the use of radiation-sensitive indicators for the visual and qualitative indication that the insects have been irradiated (see ISO/ASTM Guide 51539).
1.8 This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
1.9 This international standard was developed in accordance with internationally recognized principles on standardization established in the Decision on Principles for the Development of International Standards, Guides and Recommendations issued by the World Trade Organization Technical Barriers to Trade (TBT) Committee.
|
Published |
2022-08 |
Edition : 4 |
Number of pages : 12 |
Technical Committee |
07.080
Biology. Botany. Zoology
;
17.240
Radiation measurements
|
| ISO/ASTM 51956:2002 |
Practice for use of thermoluminescence-dosimetry (TLD) systems for radiation processing |
ISO/ASTM 51956 covers procedures for the use of thermoluminescence dosimeters (TLDs) utilized as routine dosimeters to determine the absorbed dose in a material irradiated by ionizing radiation. Examples of materials useful as TLDs include LiF, CaF 2, CaSO4, Li2B4O7 and Al2O3.
Although some elements of the procedures have broader application, the specific area of concern is radiation processing of materials such as blood products, food and insects for sterile release programmes. This practice is applicable to the measurement of absorbed dose in materials irradiated by gamma rays, X rays and electrons. Source energies covered are from 0,1 MeV to 50 MeV for photons and electrons. The range of absorbed dose covered is approximately from 1 Gy to 105 Gy (10 2 rad to 107 rad), and the range of absorbed dose rates is approximately from 10-2 Gy s-1 to 1010 Gy s-1 (1 rad s-1 to 1012 rad s-1). Absorbed dose and absorbed dose-rate measurements in materials subjected to neutron irradiation are not covered in this practice.
The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.
|
Withdrawn |
2002-03 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 16467:2003 |
Packaging — Transport packages for dangerous goods — Test methods for IBCs |
ISO 16467:2003 specifies the design type test requirements for Intermediate Bulk Containers (IBCs) intended for use in the transport of dangerous goods.
|
Withdrawn |
2003-10 |
Edition : 1 |
Number of pages : 31 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO/ASTM 51956:2013 |
Practice for use of a thermoluminescence-dosimetry system (TLD system) for radiation processing |
ISO/ASTM 51956:2013 covers procedures for the use of thermoluminescence dosimeters (TLDs) to measure the absorbed dose in materials irradiated by photons or electrons in terms of absorbed dose to water. Thermoluminescence-dosimetry systems (TLD systems) are generally used as routine dosimetry systems.
The thermoluminescence dosimeter (TLD) is classified as a type II dosimeter on the basis of the complex effect of influence quantities on the dosimeter response.
ISO/ASTM 51956:2013 is one of a set of standards that provides recommendations for properly implementing dosimetry in radiation processing, and describes a means of achieving compliance with the requirements of ISO/ASTM 52628 "Practice for Dosimetry in Radiation Processing" for a TLD system.
It is intended to be read in conjunction with ISO/ASTM 52628.
|
Published |
2013-11 |
Edition : 3 |
Number of pages : 8 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 52116:2002 |
Practice for dosimetry for a self-contained dry-storage gamma-ray irradiator |
ISO/ASTM 52116:2002 outlines dosimetric procedures to be followed with self-contained dry-storage gamma-ray irradiators. ISO/ASTM 52116:2002 covers dosimetry in the use of dry-storage gamma-ray irradiators, namely self-contained dry-storage
137
Cs or
60
Co irradiators (shielded freestanding irradiators). It does not cover underwater pool sources, panoramic gamma-ray sources such as those raised mechanically or pneumatically to irradiate isotropically into a room or through a collimator, nor does it cover self-contained bremsstrahlung x-ray units.
|
Withdrawn |
2002-12 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 52116:2013 |
Practice for dosimetry for a self-contained dry-storage gamma irradiator |
ISO/ASTM 52116:2013 outlines dosimetric procedures to be followed with self-contained dry-storage gamma irradiators. For irradiators used for routine processing, procedures are given to ensure that product processed will receive absorbed doses within prescribed limits.
|
Published |
2013-04 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 52303:2015 |
Guide for absorbed-dose mapping in radiation processing facilities |
ISO/ASTM 52303:2015 provides guidance in determining absorbed-dose distributions (mapping) in products, materials or substances irradiated in gamma, X-ray (bremsstrahlung) and electron beam facilities.
|
Published |
2015-07 |
Edition : 1 |
Number of pages : 11 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 52628:2013 |
Standard practice for dosimetry in radiation processing |
ISO/ASTM 52628:2013 describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E61 series of dosimetry standards. In addition, it provides guidance on the selection of dosimetry systems and directs the user to other standards that provide specific information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications.
ISO/ASTM 52628:2013 applies to dosimetry for radiation processing applications using electrons or photons (gamma- or X-radiation).
ISO/ASTM 52628:2013 addresses the minimum requirements of a measurement management system, but does not include general quality system requirements.
|
Withdrawn |
2013-11 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 52628:2020 |
Standard practice for dosimetry in radiation processing |
This practice describes the basic requirements that apply when making absorbed dose measurements in accordance with the ASTM E61 series of dosimetry standards. In addition, it provides guidance on the selection of dosimetry systems and directs the user to other standards that provide specific information on individual dosimetry systems, calibration methods, uncertainty estimation and radiation processing applications.
This practice applies to dosimetry for radiation processing applications using electrons or photons (gamma- or
X-radiation).
This practice addresses the minimum requirements of a measurement management system, but does not include general quality system requirements.
This practice does not address personnel dosimetry or medical dosimetry.
This practice does not apply to primary standard dosimetry systems.
This standard does not purport to address all of the safety concerns, if any, associated with its use. It is the responsibility of the user of this standard to establish appropriate safety, health, and environmental practices and determine the applicability of regulatory limitations prior to use.
|
Published |
2020-04 |
Edition : 2 |
Number of pages : 13 |
Technical Committee |
17.240
Radiation measurements
|
| ISO/ASTM 52701:2013 |
Guide for performance characterization of dosimeters and dosimetry systems for use in radiation processing |
ISO/ASTM 52701:2013 provides guidance on determining the performance characteristics of dosimeters and dosimetry systems used in radiation processing.
ISO/ASTM 52701:2013 describes the influence quantities that might affect the performance of dosimeters and dosimetry systems and that should be considered during dosimeter/dosimetry system characterization.
Users of ISO/ASTM 52701:2013 are directed to existing standards and literature for procedures to determine the effects from individual influence quantities and from combinations of more than one influence quantity.
Guidance is provided regarding the roles of the manufacturers, suppliers, and users in the characterization of dosimeters and dosimetry systems.
|
Published |
2013-11 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
17.240
Radiation measurements
|
| ISO 13464:1998 |
Simultaneous determination of uranium and plutonium in dissolver solutions from reprocessing plants — Combined method using K-absorption edge and X-ray fluorescence spectrometry |
|
Published |
1998-04 |
Edition : 1 |
Number of pages : 13 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 13274:2013 |
Packaging — Transport packaging for dangerous goods — Plastics compatibility testing for packaging and IBCs |
ISO 13274:2013 specifies the requirements and test methods for compatibility testing of plastics packagings/Intermediate Bulk Containers (IBCs) and composite packagings/IBCs with plastics inners containing liquids. The testing involves storage with the liquid to be transported. For polyethylene-based packaging, testing with a standard liquid as defined in The European Agreement concerning the International Carriage of Dangerous Goods by Road may be undertaken. Annex B describes small-scale laboratory tests that may be used to determine the assimilation of those products to be carried with the standard liquids.
Where there is any contradiction between ISO 13274:2013 and any applicable regulation, the regulation always takes precendence.
|
Published |
2013-08 |
Edition : 1 |
Number of pages : 27 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 13274:2013/Cor 1:2014 |
Packaging — Transport packaging for dangerous goods — Plastics compatibility testing for packaging and IBCs — Technical Corrigendum 1 |
|
Published |
2014-04 |
Edition : 1 |
Number of pages : 1 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 16101:2004 |
Packaging — Transport packaging for dangerous goods — Plastics compatibility testing |
ISO 16101:2004 specifies the requirements and test methods for compatibility testing of polyethylene based plastics packagings and composite packagings with plastic inners containing liquids. The testing involves storage with the packaged substance, or with a standard liquid as defined in Annex A. Annex B describes small scale laboratory tests which may be used to determine the assimilation of those products to be carried with the standard liquids.
|
Withdrawn |
2004-09 |
Edition : 1 |
Number of pages : 67 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 16103:2005 |
Packaging — Transport packaging for dangerous goods — Recycled plastics material |
ISO 16103:2005 specifies the requirements and test methods for the production of recycled plastics materials to be used for packagings for the transport of dangerous goods. This includes guidance on the quality assurance programme.
|
Published |
2005-07 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 16104:2003 |
Packaging — Transport packaging for dangerous goods — Test methods |
ISO 16104:2003 specifies the design type test requirements for packagings intended for use in the transport of dangerous goods.
|
Withdrawn |
2003-05 |
Edition : 1 |
Number of pages : 47 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 16106:2006 |
Packaging — Transport packages for dangerous goods — Dangerous goods packagings, intermediate bulk containers (IBCs) and large packagings — Guidelines for the application of ISO 9001 |
ISO 16106:2006 gives guidance on quality management provisions applicable to the manufacture, measuring and monitoring of design type approved dangerous goods packagings, intermediate bulk containers (IBCs) and large packagings.
ISO 16106:2006 can only be used in combination with ISO 9001:2000; it is not a stand-alone document.
It does not apply to design type testing, for which reference is made to 6.1.5, 6.5.4 and 6.6.5 of the United Nations Recommendations on the Transport of Dangerous Goods. Model Regulations, fourteenth revised edition.
|
Withdrawn |
2006-03 |
Edition : 1 |
Number of pages : 27 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 16106:2020 |
Transport packages for dangerous goods — Dangerous goods packagings, intermediate bulk containers (IBCs) and large packagings — Guidelines for the application of ISO 9001 |
This document gives guidance on the application of a quality management system in the manufacture, measuring and monitoring of design type approved dangerous goods packaging, intermediate bulk containers (IBCs) and large packaging.
This document does not include guidance specific to other management systems, such as those for environmental management, occupational health and safety management, or financial management.
It is applicable to an organization that:
a) needs to demonstrate its ability to consistently provide products and services that meet customer and applicable statutory and regulatory requirements; and
b) aims to enhance customer satisfaction through the effective application of the system, including processes for improvement of the system and the assurance of conformity to customer and applicable statutory and regulatory requirements.
All the guidance in this document is generic and intended to be applicable to any organization, regardless of its type or size, or the products and services it provides.
NOTE In this document, the terms "product" or "service" only apply to products and services intended for, or required by, a customer.
It does not apply to design type testing, for which reference is made to 6.1.5, 6.3.5, 6.5.6 and 6.6.5 of the UN Model Regulations[27].
|
Published |
2020-02 |
Edition : 2 |
Number of pages : 55 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 204:1997 |
Metallic materials — Uninterrupted uniaxial creep testing in tension — Method of test |
|
Withdrawn |
1997-03 |
Edition : 1 |
Number of pages : 12 |
Technical Committee |
77.040.10
Mechanical testing of metals
|
| ISO 16495:2022 |
Packaging — Transport packaging for dangerous goods — Test methods |
This document specifies the information needed for the design type testing of packaging, intermediate bulk containers (IBCs) and large packaging intended for use in the transport of dangerous goods.
NOTE 1 This document can be used in conjunction with one or more of the international regulations set out in the Bibliography.
NOTE 2 The term “packaging” includes packaging for Class 6.2 infectious substances according to the United Nations.
|
Published |
2022-05 |
Edition : 2 |
Number of pages : 44 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 16883:2007 |
Packaging — Transport packages for dangerous goods — Test methods for large packagings |
ISO 16883:2007 specifies the design type test requirements for large packagings intended for use in the transport of dangerous goods.
|
Withdrawn |
2007-06 |
Edition : 1 |
Number of pages : 28 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 23667:2007 |
Packaging — Transport packaging for dangerous goods — Rigid plastics and plastics composite IBCs — Compatibility testing |
ISO 23667:2006 specifies the requirements and test methods for compatibility testing of polyethylene-based plastics Intermediate Bulk Containers (IBCs) and composite IBCs with plastics inners containing liquids. The testing involves storage with the packaged substance, or with a standard liquid as defined in Annex A. Annex B describes small scale laboratory tests, which may be used to determine the assimilation of those products to be carried with the standard liquids.
|
Withdrawn |
2007-07 |
Edition : 1 |
Number of pages : 82 |
Technical Committee |
13.300
Protection against dangerous goods
;
55.020
Packaging and distribution of goods in general
|
| ISO 1709:1975 |
Nuclear energy — Fissile materials — Principles of criticality safety in handling and processing |
|
Withdrawn |
1975-10 |
Edition : 1 |
Number of pages : 3 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 1709:1995 |
Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing |
Specifies the basic principles and limitations which govern operations with fissile materials. Describes general criticality safety criteria for equipment design and for the development of operating controls. Does not cover quality assurance requirements or details of equipment or operational procedures, does not deal with the effects of radiation on man or materials.These criteria apply to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear facilities. Replaces the first edition, which has been technically revised.
|
Withdrawn |
1995-10 |
Edition : 2 |
Number of pages : 4 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 1709:2018 |
Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing |
ISO 1709:2018 specifies the basic principles and limitations which govern operations with fissile materials. It discusses general nuclear criticality safety criteria for equipment design and for the development of operating controls, while providing guidance for the assessment of procedures, equipment, and operations. It does not cover specific quality assurance requirements or details of equipment or operational procedures.
ISO 1709:2018 does not deal with the issues associated with administrative criteria relating to nuclear criticality safety. These issues are covered by ISO 14943. It does not cover the effects of radiation on man or materials, unless the material properties affect nuclear criticality safety.
These criteria apply to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear establishments. They are concerned with the limitations which are imposed on operations because of the properties of these materials which permit them to support nuclear chain reactions. These principles apply to quantities of fissile nuclides in which nuclear criticality safety is required to be established.
ISO 1709:2018 can also be applied to the transport of fissile materials outside the boundaries of nuclear establishments.
|
Published |
2018-02 |
Edition : 3 |
Number of pages : 9 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 1709:2018/Amd 1:2022 |
Nuclear energy — Fissile materials — Principles of criticality safety in storing, handling and processing — Amendment 1: Methods of control and safety equipment |
|
Published |
2022-08 |
Edition : 3 |
Number of pages : 1 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO/CD 6863 |
Preparation of Plutonium and Uranium spikes for Isotope Dilution Mass Spectrometry (IDMS) |
This method applies to the preparation and validation of the spikes used for the measurement of the concentration of uranium and/or plutonium in input solutions of irradiated Magnox and light water reactor fuels (boiling water reactor or pressurized water reactor), in final products at spent-fuel reprocessing plants and in feed and products of MOX and uranium fuel fabrication by isotope dilution mass spectrometry (IDMS).
|
Under development |
|
Edition : 1 |
|
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 13465:1997 |
Determination of neptunium in nitric acid solutions by molecular absorption spectrophotometry |
|
Withdrawn |
1997-05 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7097-1:2004 |
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 1: Iron(II) reduction/potassium dichromate oxidation titrimetric method |
ISO 7097-1:2004 describes an analytical method for the determination of uranium in pure product material samples such as U metal, UO2, UO3, uranyl nitrate hexahydrate, uranium hexafluoride and U3O8 from the nuclear fuel cycle. This procedure is sufficiently accurate and precise to be used for nuclear materials accountability. This method can be used directly for the analysis of most uranium and uranium oxide nuclear reactor fuels, either irradiated or unirradiated, and of uranium nitrate product solutions. Fission products equivalent to up to 10 % burn-up of heavy atoms do not interfere, and other elements which could cause interference are not normally present in sufficient quantity to affect the result significantly. The method recommends that an aliquot of sample is weighed and that a mass titration is used, in order to obtain improved precision and accuracy. This does not preclude the use of any alternative technique which could give equivalent performance. As the performance of some steps of the method is critical, the use of some automatic device has some advantages, mainly in the case of routine analysis.
|
Published |
2004-07 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7097-2:2004 |
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method |
ISO 7097:Part 2 describes an analytical method for the determination of uranium in pure product material samples such as U metal, UO2, UO3, uranyl nitrate hexahydrate, uranium hexafluoride and U3O8 from the nuclear fuel cycle. This procedure is sufficiently accurate and precise to be used for nuclear materials accountability.
This method does not generate a toxic mixed waste as does the potassium dichromate titration. The method may not be applied to scrap or waste samples until such time as it is qualified by obtaining results statistically equivalent to those obtained by the potassium dichromate method on the same sample types.
The method recommends that an aliquot of sample is weighed and that a mass titration is used, in order to obtain improved precision and accuracy. This does not preclude the use of any alternative techniques which could give equivalent performance. As the performance of some steps of the method is critical, the use of some automatic device has some advantages, mainly in the case of routine analysis.
|
Withdrawn |
2004-07 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7097-2:2022 |
Nuclear fuel technology — Determination of uranium in solutions, uranium hexafluoride and solids — Part 2: Iron(II) reduction/cerium(IV) oxidation titrimetric method |
This document describes an analytical method for the determination of uranium in samples from pure product materials such as U metal, UO2, UO3, U3O8, uranyl nitrate hexahydrate and uranium hexafluoride from the nuclear fuel cycle. This procedure is sufficiently accurate and precise to be used for nuclear materials accountability. This method can be used directly for the analysis of most uranium and uranium oxide nuclear reactor fuels, either irradiated or un-irradiated, and of uranium nitrate product solutions. Fission products equivalent to up to 10 % burn-up of heavy atoms do not interfere, and other elements which could cause interference are not normally present in sufficient quantity to affect the result significantly. The method recommends that an aliquot of sample is weighed and that a mass titration is used, in order to obtain improved precision and accuracy. This does not preclude the use of alternative techniques which could give equivalent performance. The use of automatic device(s) in the performance of some critical steps of the method has some advantages, mainly in the case of routine analysis.
This method does not generate a toxic mixed waste as does the potassium dichromate titration in ISO 7097-1.
|
Published |
2022-11 |
Edition : 2 |
Number of pages : 17 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7097:1983 |
Determination of uranium in reactor fuel solutions and in uranium product solutions — Iron (II) sulfate reduction/potassium dichromate oxidation titrimetric method |
Specifies an analytical method for the accurate and precise determination of uranium in solutions of reactor fuels fed to reprocessing plants and in the uranyl(VI) nitrate product solutions from such plants. The method can be used directly for the analysis of nitric acid solution of most uranium and uranium/plutonium oxide reactor fuels, either irradiated or unirradiated. Fission products equivalent to up to 10 % burn-up of heavy atoms do not interfere.
|
Withdrawn |
1983-12 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7195:1993 |
Packaging of uranium hexafluoride (UF6) for transport |
Specifies requirements concerning the design, manufacture and testing of transport cylinders and packaging, the in-service testing and shipping requirements. Annex A includes principles for the safe handling of UF6, annex B gives typical examples of sampling and transport cylinders, valves and packaging, annex C describes properties of UF6, its reaction products and associated hazards.
|
Withdrawn |
1993-10 |
Edition : 1 |
Number of pages : 40 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7195:2005 |
Nuclear energy — Packaging of uranium hexafluoride (UF6) for transport |
ISO 7195:2005 specifies requirements for packaging of uranium hexafluoride (UF6) for transport.
It applies to packages designed to contain uranium hexafluoride in quantities of 0,1 kg or more; design, manufacture, inspection and testing of new cylinders and protective packagings; maintenance, repair, inspection and testing of cylinders and protective packagings; and in-service inspection and testing requirements for cylinders and protective packagings.
|
Withdrawn |
2005-09 |
Edition : 2 |
Number of pages : 72 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7195:2020 |
Nuclear energy — Packagings for the transport of uranium hexafluoride (UF6) |
This document provides the following:
— specifications for cylinders for the transport of uranium hexafluoride (UF6) to provide compatibility among different users,
— description of cylinder designs, but is not intended to develop new designs,
— fabrication requirements for the procurement of new cylinders designed for the transport of 0,1 kg or more of uranium hexafluoride,
— fabrication requirements for the procurement of new valve protections, valves and plugs, and
— requirements for cylinders and valve protections in service.
|
Published |
2020-11 |
Edition : 3 |
Number of pages : 91 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7476:1990 |
Determination of uranium in uranyl nitrate solutions of nuclear grade quality — Gravimetric method |
Gives a precise and accurate gravimetric method for determining the uranium content. Non-volatile impurities influence the accuracy of the method. Specifies principle, interferences, reagents, apparatus, procedure, expression of results and test report.
|
Withdrawn |
1990-12 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 7476:2003 |
Nuclear fuel technology — Determination of uranium in uranyl nitrate solutions of nuclear grade quality — Gravimetric method |
ISO 7476:2003 specifies a precise and accurate gravimetric method for determining the mass fraction of uranium in uranyl nitrate solutions of nuclear grade quality containing more than 100 g/kg of uranium.
Non-volatile impurities influence the accuracy of the method.
|
Published |
2003-11 |
Edition : 2 |
Number of pages : 6 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 8298:1987 |
Determination of plutonium in nitric acid solutions — Method by oxidation by cerium(IV), reduction by iron(II) ammonium sulfate and amperometric back-titration with potassium dichromate |
|
Withdrawn |
1987-02 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 8298:2000 |
Nuclear fuel technology — Determination of milligram amounts of plutonium in nitric acid solutions — Potentiometric titration with potassium dichromate after oxidation by Ce(IV) and reduction by Fe(II) |
|
Published |
2000-03 |
Edition : 2 |
Number of pages : 10 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 8299:1993 |
Determination of isotopic content and concentration of uranium and plutonium in nitric acid solution — Mass spectrometric method |
The method is based on isotope ratio measurements in solutions by thermal ionization mass spectrometry. Includes the following steps: dilution, spike addition, isotope exchange chemistry, ion exchange purification/separation, preparation of filaments, mass spectrometric measurements and calculation of isotopic and elemental concentrations. Pu 238 is determined by means of alpha spectrometry if interferences from U 238 cannot be eliminated. Is applicable to solutions of irradiated fuels from boiling water or pressurized water reactors and, after modification of chemical separation and spike solution, also to other types of fuel.
|
Withdrawn |
1993-05 |
Edition : 1 |
Number of pages : 14 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 8299:2005 |
Nuclear fuel technology — Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry |
ISO 8299:2005 applies to the measurement of the isotopic composition and the concentration of uranium and plutonium in input solutions of irradiated Magnox and light water reactor fuels (boiling water reactor or pressurized water reactor), in final products at spent-fuel reprocessing plants and in feed and products of MOX and uranium fuel fabrication. The method is applicable to other fuels, but the chemical separation and spike solution are, if necessary, adapted to suit each type of fuel.
|
Withdrawn |
2005-02 |
Edition : 2 |
Number of pages : 22 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 8299:2019 |
Nuclear fuel technology — Determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry |
This document specifies a method for the determination of the isotopic and elemental uranium and plutonium concentrations of nuclear materials in nitric acid solutions by thermal-ionization mass spectrometry.
The method applies to uranium and plutonium isotope composition and concentration measurement of irradiated Magnox and light water reactor fuels (boiling water reactor or pressurized water reactor), in final products at spent-fuel reprocessing plants, and in feed and products of MOX and uranium fuel fabrication. The method is applicable to other fuels, but the chemical separation and spike solution are, if necessary, adapted to suit each type of fuel.
|
Published |
2019-01 |
Edition : 3 |
Number of pages : 25 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 8300:1987 |
Determination of plutonium content in plutonium dioxide (PuO2) of nuclear grade quality — Gravimetric method |
The plutonium dioxide has to contain less than 0,5 % of non-volatile impurities. The content of these impurities shall be measured and a correction made to allow for them. The method is used to cross-check accountancy analyses of plutonium dioxide for safeguard purposes. Principle of the method, interferences, reagents, apparatus, procedure and expression of results are described.
|
Withdrawn |
1987-03 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 8425:2013 |
Nuclear fuel technology — Determination of plutonium in pure plutonium nitrate solutions — Gravimetric method |
ISO 8425:2013 specifies a precise and accurate gravimetric method for determining the concentration of plutonium in pure plutonium nitrate solutions and reference solutions, containing between 100 g and 300 g of plutonium per litre, in a nitric acid medium.
|
Published |
2013-12 |
Edition : 2 |
Number of pages : 6 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9005:1994 |
Uranium dioxide powder and sintered pellets — Determination of oxygen/uranium atomic ratio — Amperometric method |
Specifies an analytical method for the determination of the oxygen/uranium ratio in uranium dioxide powder and sintered pellets. The method is applicable to reactor grade samples of hyperstoichiometric uranium dioxide powder and pellets. The limit of detection for deviation from stoichiometric composition is 2,002 for uranium dioxide powder and 2,000 2 for sintered pellets.
|
Withdrawn |
1994-10 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9005:2007 |
Nuclear energy — Uranium dioxide powder and sintered pellets — Determination of oxygen/uranium atomic ratio by the amperometric method |
ISO 9005:2007 specifies an analytical method for the determination of the oxygen/uranium ratio in uranium dioxide powder and sintered pellets.
The method is applicable to reactor grade samples of hyper-stoichiometric uranium dioxide powder and pellets. The presence of reducing agents or residual organic additives invalidates the procedure.
|
Published |
2007-03 |
Edition : 2 |
Number of pages : 11 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9006:1994 |
Uranium metal and uranium dioxide powder and pellets — Determination of nitrogen content — Method using ammonia-sensing electrode |
Specifies an analytical method for determining the nitrogen content in uranium metal and uranium dioxide powder and pellets. Applicable to the determination of nitrogen, present as nitride.
|
Published |
1994-10 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9161:2004 |
Uranium dioxide powder — Determination of apparent density and tap density |
ISO 9161:2004 specifies a method of determining the apparent density and tap density of free-flowing uranium dioxide (UO2) powder which will be used for pelleting and sintering of UO2 pellets as a nuclear fuel.
The method specified by ISO 9161:2004 can be used for different UO2 powder types including grains, granules, spheres or other kinds of particles. The method can also be applied to other fuel powders as PuO2, ThO2 and powder mixtures as UO2-PuO2 and UO2-Gd2O3.
|
Withdrawn |
2004-09 |
Edition : 1 |
Number of pages : 6 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9161:2019 |
Uranium dioxide powder — Determination of apparent density and tap density |
This document specifies a method of determining the apparent density and tap density of free-flowing uranium dioxide (UO2) powder which will be used for pelleting and sintering of UO2 pellets as a nuclear fuel.
This method can be used for different UO2 powder types including grains, granules, spheres or other kinds of particles. The method can also be applied to other fuel powders as PuO2, ThO2 and powder mixtures as UO2-PuO2 and UO2-Gd2O3.
This document is based on the principle of using a flowmeter funnel (see 4.1). Other measurement apparatus, such as a Scott volumeter, can also be used.
|
Published |
2019-02 |
Edition : 2 |
Number of pages : 7 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9278:1992 |
Uranium dioxide pellets — Determination of density and amount of open and closed porosity — Boiling water method and penetration immersion method |
Describes for two methods the principle, the apparatus, the procedure of the boiling water method and of the m-Xylene impregnation method, the precision, the expression of results and the contents of the test report.
|
Withdrawn |
1992-03 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9278:2008 |
Nuclear energy - Uranium dioxide pellets — Determination of density and volume fraction of open and closed porosity |
ISO 9278:2008 specifies a method for determining the bulk density and the amount of open and closed porosity of sintered UO2 pellets. The method can be applied to other materials, for example green pellets, and UO2‑PuO2 or UO2‑Gd2O3 pellets.
|
Published |
2008-12 |
Edition : 2 |
Number of pages : 10 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9279:1992 |
Uranium dioxide pellets — Determination of density and total porosity — Mercury displacement method |
Describes the principle, the apparatus, the procedure, the expression of results and the contents of the test report.
|
Published |
1992-03 |
Edition : 1 |
Number of pages : 4 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9463:1990 |
Nitric acid feed solutions from reprocessing plants — Spectrophotometric determination of plutonium after oxidation to plutonium(VI) |
The method is applicable, without interference, in the presence of numerous cations, it is applicable to test portions containing between 0,5 mg and 2,5 mg of plutonium. Specifies principle, chemical conditions, reagents, apparatus, operating procedure, expression of results and interferences.
|
Withdrawn |
1990-12 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9463:2009 |
Nuclear energy — Nuclear fuel technology — Determination of plutonium in nitric acid solutions by spectrophotometry |
ISO 9463:2009 specifies an analytical method by spectrophotometry for determining the plutonium concentration of nitric acid solutions in reprocessing plants. The method is applicable, without interference, in the presence of numerous cations, with a standard deviation of about 5 %, where the concentration of plutonium in the solution is at least 0,5 mg·l-1.
|
Withdrawn |
2009-08 |
Edition : 2 |
Number of pages : 8 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9463:2019 |
Nuclear energy — Nuclear fuel technology — Determination of plutonium in nitric acid solutions by spectrophotometry |
This document specifies an analytical method by spectrophotometry, for determining the plutonium concentration in nitric acid solutions, with spectrophotometer implemented in hot cell and glove box allowing the analysis of high activity solutions. Commonly, the method is applicable, without interference, even in the presence of numerous cations, for a plutonium concentration higher than 0,5 mg·l−1 in the original sample with a standard uncertainty, with coverage factor k = 1, less than 5 %.
The method is intended for process controls at the different steps of the process in a nuclear fuel reprocessing plant or in other nuclear facilities.
|
Published |
2019-01 |
Edition : 3 |
Number of pages : 12 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9889:1994 |
Determination of carbon content in uranium dioxide powder and sintered pellets — Resistance furnace combustion — Titrimetric/coulometric/infrared absorbtion method |
Specifies a titrimetric/coulometric/infrared absorption method for determining the carbon content in uranium dioxide powder and sintered pellet. Applicable to the determination of 5 µg to 500 µg of carbon in uranium dioxide powder and pellets. Interference from sulfur and halogens is prevented by the use of appropriate traps.
|
Published |
1994-12 |
Edition : 1 |
Number of pages : 9 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9891:1994 |
Determination of carbon content in uranium dioxide powder and sintered pellets — High-frequency induction furnace combustion — Titrimetric/coulometric/infrared absorption methods |
The methods specified are based on heating a portion of the test sample at a temperature of at least 1100 °C to 1200 °C in an oxygen atmosphere, passing the evolved oxidation products over a purification trap filled with manganese dioxide catalyst and silver permanganate catalyst (that oxidises CO to CO2), trapping the CO2, restoring the initial pH continuously by addition of hydroxyl ions either by potentiostatic titrimetry or by coulometry, or alternatively determining the CO2 by IR absorption and integration of the signal obtained. Is applicable to the determination of 5 µg to 500 µg of carbon.
|
Published |
1994-12 |
Edition : 1 |
Number of pages : 10 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9892:1992 |
Uranium metal, uranium dioxide powder and pellets, and uranyl nitrate solutions — Determination of fluorine content — Fluoride ion selective electrode method |
Specifies an analytical method which can be used within the concentration range of 1 µg to 0,001 g of fluorine per gram of the sample. Specifies the principle, the reagents, the apparatus, the sampling, the procedure, the expression of results and the test report.
|
Published |
1992-04 |
Edition : 1 |
Number of pages : 5 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9894:1996 |
Subsampling of uranium hexafluoride in the liquid phase |
Describes a method of subsampling suitable for taking aliquots from a representative sample of uranium hexafluoride in the liquid phase. The subsamples are intended for isotopic analysis (1 g bis 3 g), impurity analysis (10 g bis 200 g) and uranium assay (5 g bis 10 g). Carbon halides, hydrocarbons and certain metal halides can be measured directly from the sample.
|
Published |
1996-06 |
Edition : 1 |
Number of pages : 8 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|
| ISO 9989:1996 |
Determination of uranium in uranium dioxide powder and pellets — Iron(II) sulfate reduction/potassium dichromate oxidation titrimetric method |
|
Withdrawn |
1996-06 |
Edition : 1 |
Number of pages : 7 |
Technical Committee |
27.120.30
Fissile materials and nuclear fuel technology
|