Metalliteollisuuden Standardisointiyhdistys

This European Standard describes a method to calculate the power and the storage volume required for the dimensioning of domestic hot water systems (DHW). The applicability ranges from direct water heaters (no storage volume and a comparatively large effective heating power) to larger storage systems with a comparatively small heating power and large storage volumes.This European Standard is applicable to the following water storage systems:- storage systems characterized by a minimal mixing zone, (such as stratified charging storage tanks or storage tanks with external heat exchangers): these systems are nominated in this standard as "charging storage systems";- storage tank water heaters and warm water storage tanks with a pronounced mixing zone (such as DHW storage tanks with internal heat exchangers), nominated in this standard as "mixed storage systems";and for different uses.The Scope also includes standardization methods for determining the energy need for domestic hot water. This European Standard covers the domestic hot water needs in buildings.The calculation of the energy needs for DHW-Systems applies to residential and non-residential buildings, a building or a zone of a building.Figure 1 shows the relative position of this standard within the set of EPB standards in the context of the modular structure as set out in EN ISO 52000-1.NOTE 1 In CEN ISO/TR 52000-2 the same table can be found, with, for each module, the numbers of the relevant EPB standards and accompanying technical reports that are published or in preparation.NOTE 2 The modules represent EPB standards, although one EPB standard may cover more than one module and one module may be covered by more than one EPB standard, for instance a simplified and a detailed method respectively. See also Clause 2 and Tables A.1 and B.1.Table 1 shows the relative position of this standard within the EPB package of standards.(...)

1.1 This Standard describes the calculation of mass flow for sizing pressure relief devices for components of refrigerating systems.NOTE The term "refrigerating system" used in this Standard includes heat pumps.1.2 This Standard describes the calculation of discharge capacities for pressure relief valves and other pressure relief devices in refrigerating systems including the necessary data for sizing these when relieving to atmosphere or to components within the system at lower pressure.1.3 This Standard specifies the requirements for selection of pressure relief devices to prevent excessive pressure due to internal and external heat sources, the sources of increasing pressure (e.g. compressor, heaters, etc.) and thermal expansion of trapped liquid.1.4 This Standard describes the calculation of the pressure loss in the upstream and downstream line of pressure relief valves and other pressure relief devices and includes the necessary data.1.5 This Standard refers to other relevant standards in Clause 5.

This document specifies the requirements for the design, manufacture and testing of valves for a ratedtemperature of -40 °C and below (cryogenic service), i.e. for operation with cryogenic fluids in additionto operation at temperatures from ambient to cryogenic.It applies to all types of cryogenic valves, including vacuum jacketed cryogenic valves up to size DN200. This document can be used as guidance for larger size valves. This document is not applicable topressure relief valves covered by ISO 21013-1.

This document specifies requirements for continuously organic coated (coil coated) steel flat products. It particularly specifies the performance requirements.The products covered are wide strip, sheet cut from wide strip, slit wide strip, strip rolled in widths less than 600 mm and cut lengths (from sheet or strip).NOTE National provisions can set up relationships between the performances of the coatings as required in this document and the outdoor atmospheres and ambiances required for a relevant building under study.This document is not applicable to continuously organic coated flat products made of:- tin mill products;- electrical steels.

This document applies to hearing aid fitting management (HAFM) services offered by hearing aid professionals (HAP) when providing benefit for their clients. The provision of hearing aids relies on the knowledge and practices of a hearing aid professional, to ensure the proper fitting and adequate service in the interest of the client with hearing loss.This document specifies general processes of HAFM from the client profile to the follow-up through administering, organising and controlling hearing aid fitting through all stages. It also specifies important preconditions such as education, facilities and systems that are required to ensure proper services.The focus of this document is the services offered to the majority of adult clients with hearing impairment. It is recognized that certain populations with hearing loss such as children, persons with other disabilities or persons with implantable devices can require services outside the scope of this document. This document generally applies to air conduction hearing aids and for the most part also to bone conduction devices.Hearing loss can be a consequence of serious medical conditions. Hearing aid professionals are not in a position to diagnose or treat such conditions. When assisting clients seeking hearing rehabilitation without prior medical examination, hearing aid professionals are expected to be observant of symptoms of such conditions and refer to proper medical care.Further to the main body of the document, which specifies the HAFM requirements and processes, several informative annexes are provided. Appropriate education of hearing aid professionals is vital for exercising HAFM. Annex A defines the competencies required for the HAFM processes. Annex B offers a recommended curriculum for the education of hearing aid professionals. Annex C is an example of an appropriate fitting room. Annex D gives guidance on the referral of clients for medical or other specialist examination and treatment. Annex E is a recommendation for important information to be exchanged with the client during the process of HAFM. Annex F is a comprehensive terminology list offering definitions of the most current terms related to HAFM.It is the intention that these annexes be helpful to those who wish to deliver HAFM of the highest quality.

The purpose of this part of ISO 10360 is to define metrological characteristics and methods for testing coordinate measuring systems (CMSs) using the principle of computed tomography (CT) as a single sensor which are dedicated to dimensional measurements of technical workpieces. This excludes medical imaging, medical dimensional measurements and as well non-destructive (material) testing applications of CT (e.g. defect analyses). The intention of this part of ISO 10360 is to achieve comparability with the characteristics of coordinate measuring systems with tactile and with optical sensors. The characteristics described in this part serve both for the specification of coordinate measuring systems using the principle of computed tomography and for the comparison between various coordinate measurement systems. This standard is intentionally dedicated to the CMS using X-ray-based computed tomography where the measurements are predominantly based on the attenuation contrast visible when penetrating physical matter. This standard may also be applied to CMS using other tomographic measurement principles based on a mutual agreement. This standard covers coordinate measuring systems using sensors based on the kinematic/geometric principles of axial CT (fan and cone beam geometries) and as well helical CT as described in Annex F. This standard covers coordinate measuring systems and defines metrological characteristics and methods for testing which are intended specifically for non-gradient mono-materials which are homogeneous, i.e. cases where measurements of reference standards are performed which consist only of one (relevant) material which does not show a relevant lateral or spatial gradient in the attenuation of X-rays. This part of ISO 10360 does not define metrological characteristics and related testing methods which are dedicated to measure the influence of surface roughness on CT-based CMS measurements (cf. e.g. [XXX], [YYY] for describing the potential influence). In close reliance on ISO 10360-2 and ISO 10360-5 and as well ISO 10360-8, this standard defines the methods for acceptance testing and for the monitoring of length measurement errors and probing errors when using CT-based CMS. Therefore, this document establishes the additional aspects necessary when using CT: - Reference standards usable as alternatives to gauge blocks - Comparability of the characteristics when using alternative standards (e.g. with spherical bounding surfaces) - Comparability of the characteristics under different probing strategies (different number of points, degree of coverage of the elements to be measured) - Definition of the characteristics for various operating conditions - Notes on the treatment of affecting quantities such as environmental conditions, mathematical data filters and the nature of the measurement standard’s surface.

This European Standard specifies general construction, performance and material requirements for PN 10 thermostatic mixing valves (TMV) and includes test methods for the verification of mixed water temperature performance at the point of use below 45 °C. This does not exclude the selection of higher temperatures where available. When these devices are used to provide anti-scald protection for children, elderly and disabled persons the mixed water temperature needs to be set at a suitable bathing temperature (body temperature approximately 38 °C) as children are at risk to scalding at lower temperatures than adults. This does not obviate the need for supervision of young children during bathing.It applies to valves intended for use on sanitary appliances in kitchens, washrooms (incl. all rooms with sanitary tapware, e.g. toilets and cloakrooms) and bath rooms operating under the conditions specified in Table 1.This standard allows TMVs to supply a single outlet or a small number of outlets in a "domestic" application (e.g. one valve controlling a shower, bath, basin and/or bidet), excluding valves specifically designed for supplying a large number of outlets (i.e. for institutional use).The tests described are type tests (laboratory tests) and not quality control tests carried out during manufacture.Table 1 - Conditions of use

This European Standard specifies general construction, performance and material requirements for PN 10 thermostatic mixing valves (TMV) and includes test methods for the verification of mixed water temperature performance at the point of use below 45 °C. This does not exclude the selection of higher temperatures where available. When these devices are used to provide anti-scald protection for children, elderly and disabled persons the mixed water temperature needs to be set at a suitable bathing temperature (body temperature - 38 °C) as children are at risk to scalding at lower temperatures than adults. This does not obviate the need for supervision of young children during bathing.It applies to valves intended for use on sanitary appliances in kitchens, washrooms (incl. all rooms with sanitary tapware, e.g. toilet and cloakrooms) and bathrooms operating under the conditions specified in Table 1.This standard allows TMVs to supply a single outlet or a small number of outlets in a "domestic" application (e.g. one valve, controlling a shower, bath, basin and/or, bidet), excluding valves specifically designed for supplying a large number of outlets (i.e. for institutional use).The tests described are type tests (laboratory tests) and not quality control tests carried out during manufacture.Table 1 - Conditions of use

This document deals with all significant hazards, hazardous situations and events relevant to agglomerators for the modification of plastic scraps in its form, size and flow characteristics, when they are used as intended and under conditions of misuse which are reasonably foreseeable by the manufacturer (see Annex A). The hazards have been identified taking into account all phases of the machine life cycle according to EN ISO 12100:2010, 5.4.Machines considered in this document begin at the outer edge of the feed opening and end at the outer edge of the discharge opening.This document does not deal with:- hazards due to emissions by processing materials that could be hazardous to health;- hazards caused by ignition of flammable residues in material to be processed;- requirements for exhaust ventilation systems.This document is not applicable to agglomerators manufactured before the date of its publication.

This document covers trunnion systems used for tie-down, tilting and/or lifting of a package of radioactive material during transport operations.Aspects included are the design, manufacture, maintenance, inspection and management system. Regulations which can apply during handling operation in nuclear facilities are not addressed in document.This document does not supersede any of the requirements of international or national regulations, concerning trunnions used for lifting and tie-down.

This document describes a method for measuring 238Pu and 239 + 240 isotopes in soil by alpha spectrometry samples using chemical separation techniques.The method can be used for any type of environmental study or monitoring. These techniques can also be used for measurements of very low levels of activity, one or two orders of magnitude less than the level of natural alpha-emitting radionuclides.The test methods described in this document can also be used to measure the radionuclides in sludge, sediment, construction material and products following proper sampling procedure[2][3][4][5][7][8].The mass of the test portion required depends on the assumed activity of the sample and the desired detection limit. In practice, it can range from 0,1 g to 100 g of the test sample.

This document describes the methods for determining the activity in becquerel (Bq) of gamma-ray emitting radionuclides in test samples by gamma-ray spectrometry. The measurements are carried out in a testing laboratory following proper sample preparation. The test samples can be solid, liquid or gaseous. Applications include:— routine surveillance of radioactivity released from nuclear installations or from sites discharging enhanced levels of naturally occurring radioactive materials;— contributing to determining the evolution of radioactivity in the environment;— investigating accident and incident situations, in order to plan remedial actions and monitor their effectiveness;— assessment of potentially contaminated waste materials from nuclear decommissioning activities;— surveillance of radioactive contamination in media such as soils, foodstuffs, potable water, groundwaters, seawater or sewage sludge;— measurements for estimating the intake (inhalation, ingestion or injection) of activity of gamma-ray emitting radionuclides in the body.It is assumed that the user of this document has been given information on the composition of the test sample or the site. In some cases, the radionuclides for analysis have also been specified if characteristic limits are needed. It is also assumed that the test sample has been homogenised and is representative of the material under test.General guidance is included for preparing the samples for measurement. However, some types of sample are to be prepared following the requirements of specific standards referred to in this document. The generic recommendations can also be useful for the measurement of gamma-ray emitters in situ.This document includes generic advice on equipment selection (see Annex A), detectors (more detailed information is included in Annex D), and commissioning of instrumentation and method validation. Annex F summarises the influence of different measurement parameters on results for a typical gamma-ray spectrometry system. Quality control and routine maintenance are also covered, but electrical testing of the detector and pulse processing electronics is excluded. It is assumed that any data collection and analysis software used has been written and tested in accordance with relevant software standards such as ISO/IEC/IEEE 12207.Calibration using reference sources and/or numerical methods is covered, including verification of the results. It also covers the procedure to estimate the activity content of the sample (Bq) from the spectrum.The principles set out in this document are applicable to measurements by gamma-ray spectrometry in testing laboratories and in situ. However, the detailed requirements for in situ measurement are given in ISO 18589-7 and are outside the scope of this document.This document covers, but is not restricted to, gamma-ray emitters which emit photons in the energy range of 5 keV to 3 000 keV. However, most of the measurements fall into the range 40 keV to 2 000 keV. The activity (Bq) ranges from the low levels (sub-Bq) found in environmental samples to activities found in accident conditions and high level radioactive wastes.

This document is intended for the validation of codes used for the calculation of doses received by individuals on board aircraft. It gives guidance to radiation protection authorities and code developers on the basic functional requirements which the code fulfils.Depending on any formal approval by a radiation protection authority, additional requirements concerning the software testing can apply.

This document defines the essential technical requirements that are addressed in the process of design and construction of Generation IV (GEN IV) nuclear reactors. It does not address operation, maintenance and in-service inspection of reactors.Six reactor concepts are considered for GEN IV: the sodium fast reactor, the lead fast reactor, the gas fast reactor, the very high temperature reactor, the supercritical water reactor and the molten salt reactor.Annex A details the main characteristics for the different concepts.The scope of application of this document is limited to mechanical components related to nuclear safety and to the prevention of the release of radioactive materials— that are considered to be important in terms of nuclear safety and operability,— that play a role in ensuring leaktightness, partitioning, guiding, securing and supporting, and— that contain and/or are in contact with fluids (such as vessels, pumps, valves, pipes, bellows, box structures, heat exchangers, handling and driving mechanisms).

This document describes the principles for the measurement of the activity of 90Sr in equilibrium with 90Y and 89Sr, pure beta emitting radionuclides, in soil samples. Different chemical separation methods are presented to produce strontium and yttrium sources, the activity of which is determined using proportional counters (PC) or liquid scintillation counters (LSC). 90Sr can be obtained from the test samples when the equilibrium between 90Sr and 90Y is reached or through direct 90Y measurement. The selection of the measuring method depends on the origin of the contamination, the characteristics of the soil to be analysed, the required accuracy of measurement and the resources of the available laboratories.These methods are used for soil monitoring following discharges, whether past or present, accidental or routine, liquid or gaseous. It also covers the monitoring of contamination caused by global nuclear fallout.In case of recent fallout immediately following a nuclear accident, the contribution of 89Sr to the total amount of strontium activity will not be negligible. This standard provides the measurement method to determine the activity of 90Sr in presence of 89Sr.The test methods described in this document can also be used to measure the radionuclides in sludge, sediment, construction material and products by following proper sampling procedure.Using samples sizes of 20 g and counting times of 1 000 min, detection limits of (0,1 to 0,5) Bq·kg-1 can be achievable for 90Sr using conventional and commercially available proportional counter or liquid scintillation counter when the presence of 89Sr can be neglected. If 89Sr is present in the test sample, detection limits of (1 to 2) Bq·kg-1 can be obtained for both 90Sr and 89Sr using the same sample size, counting time and proportional counter or liquid scintillation counter as in the previous situation.

This document provides a method that allows an estimation of gross radioactivity of alpha- and beta-emitters present in soil samples. It applies, essentially, to systematic inspections based on comparative measurements or to preliminary site studies to guide the testing staff both in the choice of soil samples for measurement as a priority and in the specific analysis methods for implementation.The gross a or ß radioactivity is generally different from the sum of the effective radioactivities of the radionuclides present since, by convention, the same alpha counting efficiency is assigned for all the alpha emissions and the same beta counting efficiency is assigned for all the beta emissions.Soil includes rock from bedrock and ore as well as construction materials and products, potery, etc. using naturally occurring radioactive materials (NORM) or those from technological processes involving Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM), e.g. the mining and processing of mineral sands or phosphate fertilizer production and use.The test methods described in this document can also be used to assess gross radioactivity of alpha- and beta-emitters in sludge, sediment, construction material and products following proper sampling procedure[2][3][4][5][7][8].For simplification, the term “soil” used in this document covers the set of elements mentioned above.

This document specifies the general requirements to carry out radionuclides tests, including sampling of soil including rock from bedrock and ore as well as of construction materials and products, pottery, etc. using NORM or those from technological processes involving Technologically Enhanced Naturally Occurring Radioactive Materials (TENORM) e.g. the mining and processing of mineral sands or phosphate fertilizer production and use.For simplification, the term “soil” used in this document covers the set of elements mentioned above.This document is addressed to people responsible for determining the radioactivity present in soils for the purpose of radiation protection. This concerns soils from gardens and farmland, urban or industrial sites, as well as soil not affected by human activities.This document is applicable to all laboratories regardless of the number of personnel or the extent of the scope of testing activities. When a laboratory does not undertake one or more of the activities covered by this document, such as planning, sampling or testing, the requirements of those clauses do not apply.This document is to be used in conjunction with other parts of ISO 18589 that outline the setting up of programmes and sampling techniques, methods of general processing of samples in the laboratory and also methods for measuring the radioactivity in soil. Its purpose is the following:— define the main terms relating to soils, sampling, radioactivity and its measurement;— describe the origins of the radioactivity in soils;— define the main objectives of the study of radioactivity in soil samples;— present the principles of studies of soil radioactivity;— identify the analytical and procedural requirements when measuring radioactivity in soil.This document is applicable if radionuclide measurements for the purpose of radiation protection are to be made in the following cases:— initial characterization of radioactivity in the environment;— routine surveillance of the impact of nuclear installations or of the evolution of the general territory;— investigations of accident and incident situations;— planning and surveillance of remedial action;— decommissioning of installations or clearance of materials.

This document specifies the requirements applicable to the design and use of airborne confinement systems that ensure safety and radioprotection functions in nuclear worksites and in nuclear installations under decommissioning to protect from radioactive contamination produced: aerosol or gas.The purpose of confinement systems is to protect the workers, members of the public and environment against the spread of radioactive contamination resulting from operations in nuclear worksites and from nuclear installations under decommissioning.The confinement of nuclear worksites and of nuclear installations under decommissioning is characterized by the temporary and evolving (dynamic) nature of the operations to be performed. These operations often take place in area not specifically designed for this purpose.This document applies to maintenance or upgrades at worksites which fit the above definition.

This document specifies the dose assessment method when an RPLD is used for dosimetry audit in external high-energy X-ray beam radiotherapy.The dosimetry for electron beams and X-ray beams of stereotactic radiotherapy, gamma-ray of brachytherapy is not included in this version.This document addresses RPLD handling, measurement method, conversion of measured value to dose, necessary correction coefficient, and the performance requirements for RPLD systems, including the reader.