Metalliteollisuuden Standardisointiyhdistys

 

This document specifies methods and means of monitoring for inadvertent movement and illicit trafficking of radioactive material. It provides guidelines on the use of both stationary and portable, for example hand-held, instruments to monitor for radiation signatures from radioactive material. Emphasis is placed on the operational aspects, i.e., requirements derived for monitoring of traffic and commodities mainly at border-crossing facilities. Although the term border is used repeatedly in this document, it is meant to apply not only to international land borders but also maritime ports, airports, and similar locations where goods or individuals are being checked. This document does not specifically address the issue of detection of radioactive materials at recycling facilities, although it is recognized that transboundary movement of metals for recycling occurs, and that monitoring of scrap metals might be done at the borders of a state. This document is applicable to —    regulatory bodies and other competent authorities seeking guidance on implementation of action plans to combat illicit trafficking, —    law enforcement agencies, for example border guards, to obtain guidelines on recommended monitoring procedures, —    equipment manufacturers in order to understand minimum requirements derived from operational necessities according to this document, and —    end-users of radiation detection equipment applicable to this document.

 

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

 

This document specifies the applicable requirements related to the design and the operation of confinement and ventilation systems for fusion facilities for tritium fuels and tritium fuel handling facilities specific for fusion applications for peaceful purposes using high tritium inventories, as well as for their specialized buildings such as hot cells, examination laboratories, emergency management centres, radioactive waste treatment and storage facilities. In most countries, a tritium quantity is declared as high for tritium inventories higher than a range of 10 g to 100 g. In the tritium fusion facilities in the scope of this document, the tritium inventory is deemed to be higher than this range for the whole site. This document applies especially to confinement and ventilation systems that ensure the safety function of nuclear facilities involved in nuclear fusion with the goal to protect the workers, the public and the environment from the dissemination of radioactive contamination originating from the operation of these installations, and in particular from airborne tritium contamination with adequate confinement systems.

 

This document provides requirements and guidance regarding the use of CAAS for operations of a nuclear facility. Requirements and guidance on CAAS design are provided in the IEC 60860. This document is applicable to operations with fissile materials outside nuclear reactors but within the boundaries of nuclear establishments. This document applies when a need for CAAS has been established. Information about the need for CAAS is given in Annex C. This document does not include details of administrative steps, which are considered to be activities of a robust management system (ISO 14943 provides details of administrative steps). Details of nuclear accident dosimetry and personnel exposure evaluations are not within the scope of this document. This document is concerned with gamma and neutron radiation rate-sensing systems. Specific detection criteria can also be met with integrating systems; systems detecting either neutron or gamma radiation can also be used. Equivalent considerations then apply.

 

The purpose of this document is to give an overview of the minimum requirements for performing the dicentric assay with quality control measures using mitogen stimulated peripheral blood lymphocytes for initial assessment of individuals involved in a mass casualty scenario. The dicentric assay is the use of chromosome damage to quickly estimate approximate radiation doses received by individuals in order to supplement the early clinical categorization of casualties. This document focuses on the organizational and operational aspects of applying the dicentric assay in an initial assessment mode. The technical aspects of the dicentric assay can be found in ISO 19238. This document is applicable either to an experienced biological dosimetry laboratory working alone or to a network of collaborating laboratories (as defined in Clause 7).

 

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

 

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

 

This document specifies the general requirements for flap valves used for dust explosion isolation. An explosion isolation flap valve is a protective system, which prevents a dust explosion from propagating via connecting pipes or ducts into other parts of apparatus or plant areas. NOTE 1 An explosion isolation flap valve is also used as a process equipment (back pressure flap valve), to prevent the exposure of workers to dust cloud at workplaces when the flow is stopped in normal operation or by a process shut down. This function which is not related to explosion isolation is not in the scope of this European Standard. An explosion isolation flap valve can only stop the propagation of a dust explosion when it propagates against the direction of the normal process flow. It does not stop explosions running in the normal process flow direction. This European Standard specifies methods for evaluating the efficacy of explosion isolation flap valves. This document is applicable only to explosion isolation flap valves which are intended to avoid explosion propagation from a vessel, into other parts of the installation via connecting pipes or ducts. The standard covers isolation of such vessels that are protected by explosion venting (including flameless venting), explosion suppression or explosion-resistant design. NOTE 2 This document is only applicable to cases where the explosion starts in a vessel and not in pipes or ducting. Explosion isolation flap valves are not designed to prevent the transmission of fire or burning powder transported by the normal process flow. Very weak explosions can still lead to an isolation failure. This residual risk is not covered by this document. NOTE 3 It is necessary to take this into account in risk assessments. Explosion isolation flap valves that are kept open by a retention mechanism that prevents valve closure under gravity when there is no process air flow, require a certain explosion over-pressure to overcome the forces of the retention mechanism and to start closure. Such devices do not fall under the scope of this document, but fall under the scope of EN 15089. This document is only applicable for dust explosions. This document is not applicable for explosions of materials listed below, or for mixtures containing some of those materials: a) gases, vapours and hybrid mixtures; b) chemically unstable substances; c) explosive substances; d) pyrotechnic substances.

 

This document specifies Type S1 and Type S2 software measurement standards for verifying the software of measuring instruments. It also specifies the surface data file (SDF) format of Type S1 software measurement standards for the calibration of instruments for the measurement of surface texture by the areal method as defined in the areal surface texture chain of standards, chain link G. The SDF format is suitable for areal topography measurement data extracted with an orthogonal grid (see ISO 14406:2010, 5.2) and equidistant sampling intervals, regardless of the measurement principle.

 

This document defines terms related to the refrigerating systems and heat pumps industry as regards to safety and environmental requirements. The term "refrigerating systems" includes heat pumps and air conditioners.

 

ISO 25178-71:2017 defines Type S1 and Type S2 software measurement standards (etalons) for verifying the software of measuring instruments. It also defines the file format of Type S1 software measurement standards for the calibration of instruments for the measurement of surface texture by the areal method as defined in the areal surface texture chain of standards, chain link G. NOTE Throughout ISO 25178-71:2017, the term "softgauge" is used as a substitute for "software measurement standard Type S1".

 

 

This document specifies the general requirements involved in three-dimensional modelling for mechanical products, including the terms and definitions, the general process and requirements for modelling, requirements for model checking and model release.

 

This document provides the methods, parameter sets and models to develop and utilize a data package for a part created using AM technologies (AM part). This document is scoped to the information requirements associated with workflow of the fabrication of an AM part, from design to acceptance. Peripheral information related to entities such as organization, facility, operator, security, and others is addressed for sake of completeness; but is not the focus of this document and can be defined elsewhere. This document provides the means to develop an organizational or application-specific data package for the communication between and amongst the designer, the manufacturer, and all acceptance authorities, among other potential stakeholders. This document does not impose a plan of execution to produce an AM part, though a digital thread is provided to establish a referenceable information workflow. The requirements set forth in this document are based on the fabrication of a part using the PBF-LB/M process. While specific details directly relate to PBF-LB/M, generalized workflow requirements can be related to any AM process.

 

This document specifies a method for the measurement of effective focal spot dimensions above 0,1 mm of X-ray systems up to and including 1 000 kV X-ray voltage by means of the pinhole camera method with digital evaluation. The tube voltage applied for this measurement is restricted to 200 kV for visual film evaluation and can be selected higher than 200 kV if digital detectors are used. The imaging quality and the resolution of X-ray images depend highly on the characteristics of the effective focal spot, in particular the size and the two-dimensional intensity distribution as seen from the detector plane. Compared to the other methods specified in the EN 12543 series and the ISO 32543 series, this method allows to obtain an image of the focal spot and to see the state of it (e.g. cratering of the anode). This test method provides instructions for determining the effective size (dimensions) of standard (macro focal spots) and mini focal spots of industrial X-ray tubes. This determination is based on the measurement of an image of a focal spot that has been radiographically recorded with a “pinhole” technique and evaluated with a digital method. For the characterization of commercial X-ray tube types (i.e. for advertising or trade), the specific FS (focal spot) values of Annex A can be used.

 

This document specifies a test procedure for determination of the size of industrial radiographic gamma sources of 0,5 mm or greater, made from the radionuclides Iridium 192, Ytterbium 169, Selenium 75 or Cobalt 60, by a radiography method with X-rays. The source size of a gamma radiation source is an important factor which affects the image quality of gamma ray images. The source size is determined with an accuracy of ±10 % but typically not better than ±0,1 mm. The source size is provided by the manufacturer as the mechanical dimension of the source insert. A measurement can be required if the manufacturing process is validated or monitored after implementation of the source into the holder. This document can be used for other radionuclides after validation. The standard test method ASTM E1114 provides further information on the measurement of the Ir-192 source size, the characterization of the source shape, and its correct assembly and packaging.

 

This document specifies the measurement and test methods for general characteristics of cold formed cylindrical helical torsion springs made from round wire, excluding dynamic testing.

 

This document specifies the measurement and test methods for the general characteristics of cold formed helical compression springs made from round wire, excluding dynamic testing.

 

This document specifies the measurement and test methods for general characteristics of cold formed helical extension springs made from round wire, excluding dynamic testing.

 

This document specifies the conformance testing and marking requirements for hand torque tools used for controlled tightening of screws and nuts. It also specifies the minimum requirements for a manufacturer’s declaration of conformance for hand torque tools. This document applies to hand torque tools which are classified as indicating torque tools (Type I) and setting torque tools (Type II). NOTE          Hand torque tools covered by this document are those identified in ISO 1703:2018 by reference numbers 7 1 00 01 0 to 7 1 00 14 0 inclusive.  Torque limiting hand torque tools do not yet have reference numbers and will not do so until the next revision of ISO 1703 This document does not specify requirements of calibration certificates for hand torque tools. These are described in ISO 6789-2. This document does not specify requirements for verifying the performance of hand torque tools. These are described in ISO 6789-3.