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定价： 590元 / 折扣价： 502 元 加购物车

5.1 This test method provides for the measuring of the minimum concentration of oxygen in a flowing mixture of oxygen and nitrogen that will just support flaming combustion of plastics. Correlation with burning characteristics under actual use conditions is not implied.5.2 In this test method, the specimens are subjected to one or more specific sets of laboratory test conditions. If different test conditions are substituted or the end-use conditions are changed, it is not always possible by or from this test to predict changes in the fire-test-response characteristics measured. Therefore, the results are valid only for the fire-test-exposure conditions described in this test method.1.1 This fire-test-response standard describes a procedure for measuring the minimum concentration of oxygen, expressed as percent volume, that will just support flaming combustion in a flowing mixture of oxygen and nitrogen.1.2 This test method provides three testing procedures. Procedure A involves top surface ignition, Procedure B involves propagating ignition, and Procedure C is a short procedure involving the comparison with a specified minimum value of the oxygen index.1.3 Test specimens used for this test method are prepared into one of six types of specimens (see Table 1).1.4 This test method provides for testing materials that are structurally self-supporting in the form of vertical bars or sheet up to 10.5-mm thick. Such materials are solid, laminated or cellular materials characterized by an apparent density greater than 15 kg/m3.1.5 This test method also provides for testing flexible sheet or film materials, while supported vertically.1.6 This test method is also suitable, in some cases, for cellular materials having an apparent density of less than 15 kg/m3.NOTE 1: Although this test method has been found applicable for testing some other materials, the precision of the test method has not been determined for these materials, or for specimen geometries and test conditions outside those recommended herein.1.7 This test method measures and describes the response of materials, products, or assemblies to heat and flame under controlled conditions, but does not by itself incorporate all factors required for fire hazard or fire risk assessment of the materials, products, or assemblies under actual fire conditions.1.8 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.9 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. Specific hazards statement are given in Section 10.1.10 Fire testing is inherently hazardous. Adequate safeguards for personnel and property shall be employed in conducting these tests.NOTE 2: This test method and ISO 4589-2 are technically equivalent when using the gas measurement and control device described in 6.3.1, with direct oxygen concentration measurement.1.11 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.

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This specification covers two sizes of extra-high-strength grade of concentric-lay steel wire strand, composed of seven, zinc-coated steel wires, specifically intended for use as the supporting messenger in Figure 8-type communication and electrical cables. Steel wires shall be manufactured by the open-hearth, basic-oxygen, or electric-furnace process. Materials shall adhere to specified mechanical and physical requirements such as breaking strength, elongation, ductility, nominal diameter, and coating weight and adherence. Zinc coatings shall be continuous and of reasonably uniform thickness, and wires shall be free from imperfections not consistent with good commercial practice.1.1 This specification covers two sizes of extra-high-strength grade of concentric-lay steel wire strand, composed of seven, zinc-coated steel wires, specifically intended for use as the supporting messenger in Figure 8-type communication and electrical cables.1.2 The values stated in inch-pound units are to be regarded as standard. The values given in parentheses are mathematical conversions to SI units that are provided for information only and are not considered standard.1.3 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.

定价： 515元 / 折扣价： 438 元 加购物车

定价： 515元 / 折扣价： 438 元 加购物车

定价： 590元 / 折扣价： 502 元 加购物车

定价： 646元 / 折扣价： 550 元 加购物车

5.1 In order to demonstrate conformance to regulatory requirements and support the post-closure repository performance assessment information is required about the attributes, characteristics, and behavior of the SNF. These properties of the SNF in turn support the transport, interim storage, and repository pre-closure safety analyses, and repository post-closure performance assessment. In the United States, the interim dry storage of commercial LWR SNF is regulated per the Code of Federal Regulations, Title 10, Part 72, which requires that the cladding must not sustain during the interim storage period any “gross” damage sufficient to release fuel from the cladding into the container environment. In other countries, the appropriate governing body will set regulations regarding interim dry storage of commercial LWR SNF. However, cladding damage insufficient to allow the release of fuel during the interim storage period may still occur in the form of small cracks or pinholes that can develop into much larger defects. These cracks/pinholes could be sufficient to classify the fuel as “failed fuel” or “breached fuel” per the definitions given in Section 3 for repository disposal purposes, because they could allow contact of water vapor or liquid with the spent fuel matrix and thus provide a pathway for radionuclide release from the waste form. Therefore SNF characterization should be adequate to determine the amount of “failed fuel” for either usage as required. This could involve the examination of reactor operating records, ultrasonic testing, sipping, and analysis of the residual water and drying kinetics of the spent fuel assemblies or canisters.5.2 Regulations in each country may contain constraints and limitations on the chemical or physical (or both) properties and long-term degradation behavior of the spent fuel and HLW in the repository. Evaluating the design and performance of the waste form (WF), waste packaging (WP), and the rest of the engineered barrier system (EBS) with respect to these regulatory constraints requires knowledge of the chemical/physical characteristics and degradation behavior of the SNF that could be provided by the testing and data evaluation methods provided by this guide, using the United States as an example, as follows:5.2.1 In the United States, for example, Code of Federal Regulations, Title 10, Part 60 Sections 135 and 113 require that the WF be a material that is solid, non-particulate, non-pyrophoric, and non-chemically reactive, that the waste package contain no liquid, particulates, or combustible materials and that the materials/components of the EBS be designed to provide—assuming anticipated processes and events—substantially complete containment of the HLW for the NRC-designated regulatory period.5.2.2 In the United States, for example, Code of Federal Regulations, Title 10, Part 63 Section 113 requires that the EBS be designed such that, working in combination with the natural barriers, the performance assessment of the EBS demonstrates conformance to the annual reasonably expected individual dose protection standard of Code of Federal Regulations, Title 10, Part 63 Section 311 and the reasonably maximally exposed individual standard of Code of Federal Regulations, Title 10, Part 63 Section 312, and shall not exceed EPA dose limits for protection of groundwater of Code of Federal Regulations, Title 10, Part 63 Section 331 during the NRC-designated regulatory compliance period after permanent closure.5.2.3 In the United States, for example, Code of Federal Regulations, Title 10, Part 63 Section 114 (e), (f), and (g) and Code of Federal Regulations, Title 10, Part 63 Section 115 (c) require that a technical basis be provided for the inclusion or exclusion of degradation/alteration processes pertinent to the barriers of the EBS, and that likewise a technical basis be provided for the degradation/alteration models used in the post-closure performance assessment of the capability of the EBS barriers to isolate waste.5.3 The enhanced chemical reactivity and degraded condition of corroded/damaged uranium metal-based SNF must be accounted for in both the pre-closure safety analyses and the post-closure performance assessment of the geologic repository. An example of this would be the potential for pyrophoric behavior in uranium metal-based SNF (see Guide C1454). Due to the combustibility of the metallic uranium or uranium hydride (or both), and the enhanced aqueous dissolution rates for the exposed uranium metal, the potential for enhanced chemical activity or pyrophoric behavior must be factored into the repository or interim storage facility safety analyses, and assessments of the potential for radionuclide releases from the repository site boundary after repository closure.5.4 Characterization of several key properties of SNF may be required to support the design and performance analyses of both repository above-ground SNF receipt and lag storage facilities, the WP into which the SNF is placed, and the subsurface permanent emplacement drift EBS.5.4.1 Repository waste package design must ensure that the waste to be placed in the repository can be accommodated within the radionuclide and thermal loading ranges of the waste package drift emplacement licensing conditions. To do this the radionuclide content and oxidation rate when exposed to oxygen/water environments should be determined.5.4.2 The condition of the LWR spent fuel cladding (particularly with respect to hydride content and morphology) could potentially influence the performance of the cladding in interim storage, transportation, and geologic repository disposal. The corrosion and consequent failure rate of cladding with high hydride content may be greater than that of low or no hydride content. If the performance assessment is found to be sensitive to the failure rate of the cladding, it may be necessary to perform zirconium hydride content and orientation testing, particularly for high burnup LWR SNF.5.4.3 Metallic uranium-based spent fuel introduces aspects of chemical reactivity, such as combustibility and pyrophoricity (see C1454), that should be addressed in WP design and performance assessment, and in safety analyses associated with interim storage and transportation prior to repository emplacement. Metallic uranium-based nuclear fuel has been widely used in nuclear reactors; sometimes for commercial reactors (for example, Magnox) but more often in plutonium and tritium production reactors. The manner of discharge of metallic uranium SNF from these production reactors, and/or the manner of temporary wet storage of that portion of the spent fuel that was not reprocessed has in many instances resulted in significant corrosion and mechanical damage to the SNF assemblies. This damage has resulted in the direct exposure of the metallic uranium to the basin water. The relatively high chemical reactivity of uranium in contact with water can result in significant physical damage to the assemblies as the result of corrosion product buildup, and the creation in the exposed fuel surface and fuel matrix of uranium hydride inclusions which in turn further increase the chemical activity of the material. The reaction of this spent fuel with air, water vapor, or liquid water can introduce a significant heat source term into design basis events. In order to support the evaluation of these events, the physical condition (that is, the degree of optically/visually observable damage), the chemical oxidation kinetics, the ignition characteristics, and radionuclide release characteristics of the SNF should be investigated.5.4.4 The thermal analysis of the waste package/engineered barrier system requires quantification of the potential chemical heat source. To determine this, the amount of reactive uranium metal in the waste canisters sent to the repository should be provided so the thermal analysis of the waste package/engineered barrier system can be performed.5.4.5 Radionuclide inventories and physical/chemical characteristics are required to enable storage canister, transportation package, and WP loading and emplacement configurations to be developed.5.4.6 Repository WP materials selection and design must account for the potential interactions between the waste and WP. The potential chemical forms of the wastes must be considered, and the effects of residual water or impurities (or both) should be evaluated.5.4.7 The history of the SNF interim storage and transportation conditions prior to delivery to the repository is important whenever the storage conditions may have altered the degradation characteristics of the SNF (for example, with respect to hydride content and morphology in high burnup LWR SNF cladding). Interim dry storage of commercial SNF requires that the fuel cladding should not sustain gross damage during the storage period to the extent that fuel is released from the fuel rods into the canister. Small pinholes or cracks may exist in the cladding during the storage period without violating this interim storage requirement, but may cause the fuel to be classified as failed fuel for repository disposal purposes. The objective of drying commercial SNF fuel is thus to preclude gross damage for interim storage purposes. If the conditions of transport or interim storage are such that there is a significant potential for further degradation of the SNF or change in properties important to the repository pre-closure safety or post-closure performance analyses, the characterization should provide sufficient information to evaluate these changes.1.1 This guide provides guidance for the types and extent of testing that would be involved in characterizing the physical and chemical nature of spent nuclear fuel (SNF) in support of its interim storage, transport, and disposal in a geologic repository. This guide applies primarily to commercial light water reactor (LWR) spent fuel and spent fuel from weapons production, although the individual tests/analyses may be used as applicable to other spent fuels such as those from research reactors, test reactors, molten salt reactors and mixed oxide (MOX) spent fuel. The testing is designed to provide information that supports the design, safety analysis, and performance assessment of a geologic repository for the ultimate disposal of the SNF.1.2 The testing described includes characterization of such physical attributes as physical appearance, weight, density, shape/geometry, degree, and type of SNF cladding damage. The testing described also includes the measurement/examination of such chemical attributes as radionuclide content, microstructure, and corrosion product content, and such environmental response characteristics as drying rates, oxidation rates (in dry air, water vapor, and liquid water), ignition temperature, and dissolution/degradation rates. Not all of the characterization tests described herein must necessarily be performed for any given analysis of SNF performance for interim storage, transportation, or geological repository disposal, particularly in areas where an extensive body of literature already exists for the parameter of interest in the specific service condition.1.3 It is assumed in formulating the SNF characterization activities in this guide that the SNF has been stored in an interim storage facility at some time between reactor discharge and dry transport to a repository. The SNF may have been stored either wet (for example, a spent fuel pool), or dry (for example, an independent spent fuel storage installation (ISFSI)), or both, and that the manner of interim storage may affect the SNF characteristics.1.4 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.5 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.1.6 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.

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4.1 The static chambers have several different applications:4.1.1 The static chambers can be used to compare the susceptibility of different materials to the colonization and amplification of various microorganisms under defined conditions.4.1.2 Chambers operated at high relative humidities may be used to perform worst case scenario screening tests on materials by providing an atmosphere where environmental conditions may be favorable for microbial growth.4.1.3 Use of multiple chambers with different environmental parameters, such as a range of relative humidities, permits the evaluation of multiple microenvironments and allows investigation of materials under differing environmental conditions.4.1.4 Drying requirements for wetted materials may also be investigated. This information may be relevant for determining material resistance to microbial growth after becoming wet. These conditions may simulate those where materials are subjected to water incursion through leaks as well as during remediation of a building after a fire.4.1.5 Growth rates of microorganisms on the material may also be investigated. Once it has been established that organisms are able to grow on a particular material under defined conditions, investigations into the rate of organism growth may be performed. These evaluations provide base line information and can be used to evaluate methods to limit or contain amplification of microorganisms.4.2 These techniques should be performed by personnel with training in microbiology. The individual must be competent in the use of sterile technique, which is critical to exclude external contamination of materials.1.1 Many different types of microorganisms (for example, bacteria, fungi, viruses, algae) can occupy indoor spaces. Materials that support microbial growth are potential indoor sources of biocontaminants (for example, spores and toxins) that can become airborne indoor biopollutants. This guide describes a simple, relatively cost effective approach to evaluating the ability of a variety of materials to support microbial growth using a small chamber method.1.2 This guide is intended to assist groups in the development of specific test methods for a definite material or groups of materials.1.3 Static chambers have certain limitations. Usually, only small samples of indoor materials can be evaluated. Care must be taken that these samples are representative of the materials being tested so that a true evaluation of the material is performed.1.4 Static chambers provide controlled laboratory microenvironment conditions. These chambers are not intended to duplicate room conditions, and care must be taken when interpreting the results. Static chambers are not a substitute for dynamic chambers or field studies.1.5 A variety of microorganisms, specifically bacteria and fungi, can be evaluated using these chambers. This guide is not intended to provide human health effect data. However, organisms of clinical interest, such as those described as potentially allergenic, may be studied using this approach.1.6 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.7 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.1.8 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.

定价： 590元 / 折扣价： 502 元 加购物车

定价： 646元 / 折扣价： 550 元 加购物车

定价： 646元 / 折扣价： 550 元 加购物车

4.1 This classification can be used to classify material outputs from manufacturing facilities and associated support facilities. This classification does not include classification of emissions to air or water.4.2 This classification can be used to classify discarded materials for marketing claims associated with discarded materials generation and development of consistent tracking metrics for manufacturing facilities.1.1 This standard classifies discarded materials from manufacturing facilities and associated on-site support facilities.1.2 This classification system is based on classification, location, disposition, and treatment.1.3 This classification does not purport to address or supersede proper waste disposal required by laws and regulations.1.4 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.1.5 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.

定价： 515元 / 折扣价： 438 元 加购物车

定价： 646元 / 折扣价： 550 元 加购物车

定价： 0元 / 折扣价： 0 元 加购物车

定价： 590元 / 折扣价： 502 元 加购物车