This specification covers manufacturing and joining requirements for peelable or skinned polyethylene (PE) pipe, which is PE pipe meeting the requirements of Specification D2513, with a peelable outer layer of polypropylene (PP). The peelable PP layer does not contribute to outside diameter and wall thickness used for pressure rating or tensile loading calculations.1.1 This standard specification covers manufacturing and joining requirements for peelable (skinned) polyethylene (PE) pipe, which is PE pipe meeting the requirements of Specification D2513, with a peelable outer layer of polypropylene (PP). These requirements are in addition to those in Specification D2513 for the PE pipe.1.2 The peelable PP layer does not contribute to outside diameter and wall thickness used for pressure rating or tensile loading calculations.1.3 The text of this standard references notes and footnotes which provide explanatory material. These notes and footnotes (excluding those in figures and tables) shall not be considered as requirements of the standard.1.4 Units—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.1.5 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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This specification covers the standard for iron-chromium-nickel, high-alloy tubes made by the centrifugal casting process intended for use under pressure at high temperatures. The tubing shall be supplied in the as cast condition or as cast with machining on the outside or inside surfaces. The material shall conform to the required chemical composition in carbon, manganese, silicon, chromium, nickel, phosphorus, sulfur, and molybdenum. Tension test shall be performed in the tubing at elevated temperature and shall conform to the required values in tensile strength and elongation. Tubing shall meet several tests such as; pressure test, flattening test, and mechanical test.1.1 This specification covers iron-chromium-nickel, high-alloy tubes made by the centrifugal casting process intended for use under pressure at high temperatures.1.2 The grades of high alloys detailed in Table 1 are intended for applications requiring strength and resistance to corrosion and scaling at high temperatures.1.3 Optional Supplementary Requirements S1 to S11 are provided; these call for additional tests to be made if desired.1.4 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in nonconformance with the standard.1.4.1 Within the text, the SI units are shown in brackets.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.

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4.1 Most organic liquids and solids will ignite in a pressurized oxidizing gas atmosphere if heated to a sufficiently high temperature and pressure. This procedure provides a numerical value for the temperature at the onset of ignition under carefully controlled conditions. Means for extrapolation from this idealized situation to the description, appraisal, or regulation of fire and explosion hazards in specific field situations, are not established. Ranking of the ignition temperatures of several materials in the standard apparatus is generally in conformity with field experience.4.2 The temperature at which material will ignite spontaneously (AIT) will vary greatly with the geometry of the test system and the rate of heating. To achieve good interlaboratory agreement of ignition temperatures, it is necessary to use equipment of approximately the dimensions described in the test method. It is also necessary to follow the described procedure as closely as possible.4.3 The decomposition and oxidation of some fully fluorinated materials releases so little energy that there is no clear-cut indication of ignition. Nor will there be a clear indication of ignition if a sample volatilizes, distilling to another part of the reaction vessel, before reaching ignition temperature.1.1 This test method covers the determination of the temperature at which liquids and solids will spontaneously ignite. These materials must ignite without application of spark or flame in a high-pressure oxygen-enriched environment.1.2 This test method is intended for use at pressures of 2.1 MPa to 20.7 MPa [300 psi to 3000 psi]. The pressure used in the description of the method is 10.3 MPa [1500 psi], and is intended for applicability to high pressure conditions. The test method, as described, is for liquids or solids with ignition temperature in the range from 60 °C to 500 °C [140 °F to 932 °F].NOTE 1: Test Method G72/G72M normally utilizes samples of approximately 0.20 ± 0.03-g mass, a starting pressure of 10.3 MPa [1500 psi] and a temperature ramp rate of 5 °C/min. However, Autogenous Ignition Temperatures (AIT) can also be obtained under other test conditions. Testing experience has shown that AIT testing of volatile liquids can be influenced by the sample pre-conditioning and the sample mass. This will be addressed in the standard as Special Case 1 in subsection 8.2.2. Testing experience has also shown that AIT testing of solid or non-volatile liquid materials at low pressures (that is, < 2.1 MPa) can be significantly influenced by the sample mass and the temperature ramp rate. This will be addressed in the standard as Special Case 2, in subsection 8.2.3. Since the AIT of a material is dependent on the sample mass/configuration and test conditions, any departure from the standard conditions normally used for Test Method G72/G72M testing should be clearly indicated in the test report.1.3 This test method is for high-pressure pure oxygen. The test method may be used in atmospheres from 0.5 % to 100 % oxygen.1.4 An apparatus suitable for these requirements is described. This test method could be applied to higher pressures and materials of higher ignition temperature. If more severe requirements or other oxidizers than those described are desired, care must be taken in selecting an alternative safe apparatus capable of withstanding the conditions.1.5 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in non-conformance with the standard.1.6 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.1.7 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 high strength, cold drawn or cold rolled steel wire with rectangular cross-section and round mill edge. The wire is intended for use in pre-stressed vessel and press frame windings. The steel shall be manufactured by basic oxygen, electric furnace, or vacuum induction processes and produced as ingot cast or continuous cast. Materials shall be tested for contents of carbon, manganese, phosphorus, sulphur, and silicon. A tension tests shall also be performed to evaluate mechanical properties conformance. Guidelines for workmanship, finish, and appearance are stated, as well as the inspection, certification of reports, packaging, marking, and loading for shipment.1.1 This specification covers requirements for a high strength drawn and cold rolled steel wire in two strength classes, with rectangular cross section, and round mill edge. This wire is intended for prestressed vessel and press frame windings.1.2 The values stated in either inch-pound units or SI (metric) units are to be regarded separately as standards. Within the text and tables, the SI units are shown in parentheses. The values stated in each system are not exact equivalents. Therefore, each system must be used independent of the other. Combining values from the two systems may result in nonconformance with the specification.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.

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5.1 The bulk density is an indicator of calcined petroleum coke porosity and packing capability which is an important coke property for anode production in aluminum industry. This procedure will allow an automated measurement of specific sized fractions ranging from 8 mm to 0.25 mm coke particles.5.2 Results from this test method are used in determining coke specifications, classification purposes, and for quality control.1.1 The test method covers the determination of bulk density for a specific size fraction of calcined petroleum coke using an automated pycnometer that compacts coke by applying transaxial pressure under a controlled force.1.2 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.3 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.1.4 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

This specification tackles standards for pressure consolidated powder metallurgy iron-nickel-chromium-molybdenum and nickel-chromium-molybdenum-columbium pipe flanges, fittings, valves, and parts intended for general corrosion or heat-resisting service. Compacts shall be manufactured by placing a single powder blend into a can, evacuating the can, and sealing it. The can material shall then be selected to ensure that it has no deleterious effect on the final product. The specimen shall be heated and placed under sufficient pressure for a sufficient period of time to ensure that the final consolidated part is fully dense. The powder shall be produced by vacuum melting followed by gas atomization. The heats shall be thoroughly mixed to ensure homogeneity when powder from more than one heat is used to make a blend. The material shall have the chemical compositions of carbon, manganese, silicon, phosphorus, sulfur, chromium, molybdenum, nickel, iron, cobalt, columbium, aluminum, titanium, nitrogen, and copper. Hydrostatic test shall be conducted and the specimen must show no leaks. The density test shall be performed using sample suspended from a scale and weighed in air and water using Archimede’s principle. Check Analysis shall be wholly the responsibility of the purchaser. The parts of the specimen shall be uniform in quality and condition, and shall be free from injurious imperfections.1.1 This specification covers pressure consolidated powder metallurgy nickel alloy pipe flanges, fittings, valves, and parts intended for general corrosion or heat-resisting service.1.1.1 UNS N06625 products are furnished in two grades of different heat-treated conditions:1.1.1.1 Grade 1 (annealed)—Material is normally employed in service temperatures up to 1100 °F (593 °C).1.1.1.2 Grade 2 (solution annealed)—Material is normally employed in service temperatures above 1100 °F (593 °C) when resistance to creep and rupture is required.1.2 UNS N08367 products are furnished in the solution annealed condition.1.3 UNS N06600 products are furnished in the annealed condition.1.4 UNS N06690 products are furnished in the annealed condition.1.5 UNS N07718 products are furnished in the solution annealed + precipitation hardened condition.1.6 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.1.7 The following safety hazards caveat pertains only to test methods portions, Sections 7.3 and 13, of this specification: 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 become familiar with all hazards including those identified in the appropriate Safety Data Sheet (SDS) for this product/material as provided by the manufacturer, to establish appropriate safety, health, and environmental practices, and to 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

This specification covers "fiberglass" (glass-fiber-reinforced thermosetting-resin) pressure pipe fittings for use with filament wound or centrifugally cast fiberglass pipe. The fibreglass fittings are defined by type, grade, class, category, and pressure rating: type 1 - filament-wound fittings, type 2 - compression moulded fittings, type 3 - resin transfer molded fittings, type 4 - centrifugally cast fittings, and type 5 - contact molded fittings; grade 1 - epoxy-resin, grade 2 - polyester-resin, grade 3 - phenolic-resin, grade 4 - vinylester resin, and grade 7 - furan resin; class A - no liner, class B - polyester-resin liner (nonreinforced), class C - epoxy-resin liner (nonreinforced), class D - phenolic resin liner (nonreinforced), class E - polyester-resin liner (reinforced), class F - epoxy-resin liner (reinforced), class G - phenolic resin liner, class H - thermoplastic-resin liner, class I - furan-resin liner (reinforced), class J - vinylester resin liner (nonreinforced), and class K - vinylester resin liner (reinforced); category 1 - taper-to-taper adhesive bonded joint fittings, category 2 - straight-taper adhesive-bonded joint fitting, category 3 - straight adhesive bonded joint fitting, category 5 - flanged fittings, category 6 - elastomeric sealed joints with sealant, and category 7 - elastomeric sealed joints with seals. Short-term hydrostatic strength test and cyclic or static pressure test shall be performed to meet the requirements prescribed.1.1 This specification covers “fiberglass” (glass-fiber-reinforced thermosetting-resin) fittings for use with filament wound or centrifugally cast fiberglass pipe, or both, in sizes 1 in. through 24 in. for pipe manufactured to Specification D2996 or D2997, or both.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 The following safety hazard caveat pertains only to the test method portion, Section 7, of this specification: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.NOTE 1: The term “fiberglass pipe” as described in Section 3 of this specification applies to both reinforced thermosetting resin pipe (RTRP) and reinforced polymer mortar pipe (RPMP).NOTE 2: For the purposes of this standard, polymer does not include natural polymers.NOTE 3: There is no known ISO equivalent to this standard.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： 590元 / 折扣价： 502 元 加购物车

5.1 This is a quality control test performed at the manufacturing plant to establish that the finished, shippable pipe meets the leakage limits stated in the specifications.1.1 This test method covers procedures for testing of precast concrete pipe sections, prior to delivery, where maximum field leakage rates are specified.1.2 Tests described in this standard are intended to be used at the point of manufacture of the concrete pipe and are not intended for testing installed pipe (for field tests see Practices C969 and C1214). The user of this specification is advised that individual or multiple pipe sections may be tested for the purpose of testing the pipe barrel and additionally the joints in straight alignment when multiple pipe sections are tested.1.3 Test times are based on leakage rates and therefore are proportional only to the pipe diameter and are constant for any length of test pipe or pipeline.1.4 Test times tabulated and the rate of air loss in this standard are based on successful testing of installed pipelines. However, since air and water have different physical properties, retests of some pipelines not meeting field air tests have been successful when tested with water. The leakage rates of 0.0017 CFM/ft2 and 0.0003 CFM/ft2, were determined empirically as the maximums for pipe to meet the 50 and 200 gal/(in. of internal diameter) (mile of sewer) (24h) test rates, respectively.1.5 The values stated in inch-pound units are to be regarded as standard. No other units of measurement are included in this standard.NOTE 1: The availability of this test procedure for concrete pipe varies from location to location. Check with local supplier(s) for availability and recommendations.1.6 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. See Section 6 for specific safety precautions.1.7 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 killed carbon- manganese-silicon steel plates intended for welded pressure vessels in service at moderate and lower temperatures. As a steel making practice, the steel shall be killed and shall conform to specified fine austenitic grain size requirements. Plates are normally supplied in the as-rolled condition. Plates may be ordered normalized or stress relieved, or both. The steel shall conform to the required chemical compositions. The plates, as represented by the tension test specimens, shall conform to the mechanical property requirements.1.1 This specification2 covers killed carbon-manganese-silicon steel plates intended for welded pressure vessels in service at moderate and lower temperatures.1.2 The maximum thickness of plates is limited only by the capacity of the material to meet the specified mechanical property requirements.1.3 For plates produced from coil and furnished without heat treatment or with stress relieving only, the additional requirements, including additional testing requirements and the reporting of additional test results, of Specification A20/A20M apply.1.4 The values stated in either inch-pound units or SI units are to be regarded separately as standard. Within the text, the SI units are shown in brackets. The values stated in each system are not exact equivalents; therefore, each system must be used independently of the other. Combining values from the two systems may result in nonconformance with the specification.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

5.1 This is a quality test control performed at the manufacturing plant to establish that the finished, shippable pipe meets the leakage limits stated in the specifications.1.1 This test method covers procedures for testing of precast concrete pipe sections, prior to delivery, where maximum field leakage rates are specified.1.2 Tests described in this standard are intended to be used at the point of manufacture of the concrete pipe and are not intended for testing installed pipe (for field tests see Practices C969 and C1214). The user of this specification is advised that individual or multiple pipe sections may be tested for the purpose of testing the pipe barrel and additionally the joints in straight alignment when multiple pipe sections are tested.1.3 Test times are based on leakage rates and therefore are proportional only to the pipe diameter and are constant for any length of test pipe or pipeline.1.4 Test times tabulated and the rate of air loss in this standard are based on successful testing of installed pipelines. However, since air and water have different physical properties, retests of some pipelines not meeting field air tests have been successful when tested with water. The leakage rates of 0.0017 CFM/ft2 and 0.0003 CFM/ft2, were determined empirically as the maximums for pipe to meet the 50 and 200 gal/(in. of internal diameter) (mile of sewer) (24h) test rates, respectively1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.NOTE 1: The availability of this test procedure for concrete pipe varies from location to location. Check with local supplier(s) for availability and recommendations.1.6 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. See Section 6 for specific safety precautions.1.7 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

This specification covers gray iron for castings suitable for pressure-containing parts at elevated temperatures. Castings shall be stress-relieved by placing them in a suitable furnace and heating them uniformly to the temperatures and for the times specified. Castings to be used at a particular temperature range shall undergo heat treatment and cooling. Chemical analysis shall be performed on each class of castings and shall meet the maximum requirement for carbon, phosphorus and sulfur. Iron used in supplying castings shall conform to the required tensile strength. Separately cast test bars having the required dimensions shall be poured from the same lot as the castings represented. The test bars shall be cast in dried siliceous sand molds maintained at approximately room temperature. Tension test shall be performed on each lot and materials shall conform to the tensile requirements specified.1.1 This specification2 covers gray iron for castings suitable for pressure-containing parts for use at temperatures up to 650 °F (350 °C).1.2 Classes of Iron: 1.2.1 Castings of all classes are suitable for use up to 450 °F (230 °C). For temperatures above 450 °F and up to 650 °F, only Class 40, 45, 50, 55, and 60 castings are suitable.1.2.2 Castings of all classes are suitable for use up to 230 °C. For temperatures above 230 °C and up to 350 °C, only Class 275, 300, 325, 350, 380, and 415 castings are suitable.1.3 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system may not be exact equivalents; therefore, each system shall be used independently of the other. Combining values from the two systems may result in nonconformance with the standard.1.4 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

5.1 This test method is a standard procedure for determining the resistance to water penetration under uniform or cyclic static air pressure differences of installed exterior windows, skylights, curtain walls, and doors. The air-pressure differences acting across a building envelope vary greatly. These factors should be considered fully prior to specifying the test pressure difference to be used.NOTE 1: In applying the results of tests by this test method, note that the performance of a wall or its components, or both, may be a function of proper installation and adjustment. In service, the performance will also depend on the rigidity of supporting construction and on the resistance of components to deterioration by various causes, vibration, thermal expansion and contraction, and so forth. It is difficult to simulate the identical complex wetting conditions that can be encountered in service, with large wind-blown water drops, increasing water drop impact pressures with increasing wind velocity, and lateral or upward moving air and water. Some designs are more sensitive than others to this upward moving water.NOTE 2: This test method does not identify unobservable liquid water which may penetrate into the test specimen.5.2 Laboratory tests are designed to give an indication of the performance of an assembly. Field performance may vary from laboratory performance since the supporting structure for the test specimen, methods of mounting, and sealing in the laboratory can only simulate the actual conditions that will exist in the building. Shipping, handling, installation, acts of subsequent trades, aging, and other environmental conditions all may have an adverse effect upon the performance of the installed product. This field test procedure provides a means for determining the performance of a product once installed in the building.5.3 The field test may be made at the time the window, skylight, curtain-wall, or door assemblies are initially installed and before the interior of the building is finished. At this time, it is generally easier to check the interior surfaces of the assemblies for water penetration and to identify the points of penetration. The major advantage of testing when assemblies are initially installed is that errors in fabrication or installation can be readily discovered and corrections made before the entire wall with its component assemblies is completed at which time the expense of corrective work may be increased many times.5.4 The field test may also be made after the building is completed and in service to determine whether or not reported leakage problems are due to the failure of the installed assemblies to resist water penetration at the specified static air pressure difference. Generally it is possible to conduct tests on window, skylight, and door assemblies without too much difficulty, and to identify sources of leakage. A curtain-wall assembly, on the other hand, may not be accessible from the inside without the removal of interior finished walls and ceilings. Even with removal of interior walls and ceilings, it may not be possible to observe curtain-wall surfaces behind spandrel beams. The feasibility of conducting a meaningful static air pressure difference water penetration test on an in-service building must be carefully evaluated before being specified.5.5 Weather conditions can affect the static air pressure difference measurements. If wind gusting causes pressure fluctuation to exceed ±10 % from the specified test pressure, the test should not be conducted.5.6 Generally it is more convenient to use an interior mounted pressure chamber from which air is exhausted to obtain a lower pressure on the interior surface of the specimen. A calibrated rack of nozzles is then used to spray water at the proper rate on the exterior surface. Under circumstances where it is desirable to use an exterior-mounted pressure chamber, the spray rack must be located in the pressure chamber and air supplied to maintain a higher pressure on the exterior surface. Exterior chambers are difficult to attach readily and seal to exterior surfaces.5.7 Even though the equipment requirements are similar, this procedure is not intended to measure air infiltration because of the difficulty of isolating the component air leakage from the extraneous leakage through weep holes, mullion joints, trim, or other surrounding materials.1.1 This test method covers the determination of the resistance of installed exterior windows, curtain walls, skylights, and doors to water penetration when water is applied to the outdoor face and exposed edges simultaneously with a static air pressure at the outdoor face higher than the pressure at the indoor face.1.2 This test method is applicable to any curtain-wall area or to windows, skylights, or doors alone. It is intended primarily for determining the resistance to water penetration through such assemblies for compliance with specified performance criteria, but it may also be used to determine the resistance to penetration through the joints between the assemblies and the adjacent construction. Other procedures may be appropriate to identify sources of leakage.1.3 This test method addresses water penetration through a manufactured assembly. Water that penetrates the assembly, but does not result in a failure as defined herein, may have adverse effects on the performance of contained materials such as sealants and insulating or laminated glass. This test method does not address these issues.1.4 The proper use of this test method requires a knowledge of the principles of pressure measurement.1.5 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.1.6 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. For specific hazard statements, see 7.1.1.7 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

4.1 Master Matrix—This matrix document is written as a reference and guide to the use of existing standards and to help manage the development and application of new standards, as needed for LWR-PV surveillance programs. Paragraphs 4.2 – 4.5 are provided to assist the authors and users involved in the preparation, revision, and application of these standards (see Section 6).4.2 Approach and Primary Objectives: 4.2.1 Standardized procedures and reference data are recommended in regard to (1) neutron and gamma dosimetry, (2) physics (neutronics and gamma effects), and (3) metallurgical damage correlation methods and data, associated with the analysis, interpretation, and use of nuclear reactor test and surveillance results.4.2.2 Existing state-of-the-art practices associated with (1), (2), and (3), if uniformly and consistently applied, can provide reliable (10 to 30 %, 1σ) estimates of changes in LWR-PV steel fracture toughness during a reactor’s service life (36).4.2.3 Reg. Guide 1.99 and Section III of the ASME Boiler and Pressure Vessel Code, Part NF2121 require that the materials used in reactor pressure vessels support “...shall be made of materials that are not injuriously affected by ... irradiation conditions to which the item will be subjected.”4.2.4 By the use of this series of standards and the uniform and consistent documentation and reporting of estimated changes in LWR-PV steel fracture toughness with uncertainties of 10 to 30 % (1σ), the nuclear industry and licensing and regulatory agencies can meet realistic LWR power plant operating conditions and limits, such as those defined in Appendices G and H of 10 CFR Part 50, Reg. Guide 1.99, and the ASME Boiler and Pressure Vessel Code.4.2.5 The uniform and consistent application of this series of standards allows the nuclear industry and licensing and regulatory agencies to properly administer their responsibilities in regard to the toughness of LWR power reactor materials to meet requirements of Appendices G and H of 10 CFR Part 50, Reg. Guide 1.99, and the ASME Boiler and Pressure Vessel Code.4.3 Dosimetry Analysis and Interpretation (1, 3-5, 21, 28, 29, 35, 37, 38)—When properly implemented, validated, and calibrated by vendor/utility groups, state-of-the-art dosimetry practices exist that are adequate for existing and future LWR power plant surveillance programs. The uncertainties and errors associated with the individual and combined effects of the different variables (items 1.4.1 – 1.4.10 of 1.4) are considered in this section and in 4.4 and 4.5. In these sections, the accuracy (uncertainty and error) statements that are made are quantitative and representative of state-of-the-art technology. Their correctness and use for making EOL predictions for any given LWR power plant, however, are dependent on such factors as (1) the existing plant surveillance program, (2) the plant geometrical configuration, and (3) available surveillance results from similar plants. As emphasized in Section III-A of Ref (7), however, these effects are not unique and are dependent on (1) the surveillance capsule design, (2) the configuration of the reactor core and internals, and (3) the location of the surveillance capsule within the reactor geometry. Further, the statement that a result could be in error is dependent on how the neutron and gamma ray fields are estimated for a given reactor power plant (1, 11, 28, 36, 39, 40). For most of the error statements in 4.3 – 4.5, it is assumed that these estimates are based on reactor transport theory calculations that have been normalized to the core power history (see 4.4.1.2) and not to surveillance capsule dosimetry results. The 4.3 – 4.5 accuracy statements, consequently, are intended for use in helping the standards writer and user to determine the relative importance of the different variables in regard to the application of the set of ASTM standards, Fig. 1, for (1) LWR-PV surveillance program, (2) as instruments of licensing and regulation, and (3) for establishing improved metallurgical databases.4.3.1 Required Accuracies and Benchmark Field Referencing: 4.3.1.1 The accuracies (uncertainties and errors) (Note 1) desirable for LWR-PV steel exposure definition are of the order of ±10 to 15 % (1σ) while exposure accuracies in establishing trend curves should preferably not exceed ±10 % (1σ) (1, 11, 21, 36, 40-46). In order to achieve such goals, the response of neutron dosimeters should therefore also be interpretable to accuracies within ±10 to 15 % (1σ) in terms of exposure units and be measurable to within ±5 % (1σ).NOTE 1: Uncertainty in the sense treated here is a scientific characterization of the reliability of a measurement result and its statement is the necessary premise for using these results for applied investigations claiming high or at least stated accuracy. The term error will be reserved to denote a known deviation of the result from the quantity to be measured. Errors are usually taken into account by corrections.4.3.1.2 Dosimetry “inventories” should be established in support of the above for use by vendor/utility groups and research and development organizations.4.3.1.3 Benchmark field referencing of research and utilities’ vendor/service laboratories has been completed that is:(1) Needed for quality control and certification of current and improved dosimetry practices; and(2) Extensively applied in standard and reference neutron fields, PCA, PSF, SDMF, VENUS, NESDIP, PWRs, BWRs (1), and a number of test reactors to quantify and minimize uncertainties and errors.4.3.2 Status of Benchmark Field Referencing Work for Dosimetry Detectors—PCA, VENUS, NESDIP experiments with and without simulated surveillance capsules and power reactor tests have provided data for studying the effect of deficiencies in analysis and interpretations; the PCA/PSF/SDMF perturbation experiments have provided data for more realistic PWR and BWR power plant surveillance capsule configurations and have permitted utilities’ vendor/service laboratories to test, validate, calibrate, and update their practices (1, 4, 5, 47). The PSF surveillance capsule test provided data, but of a more one-dimensional nature. PCA, VENUS, and NESDIP experimentation together with some test reactor work augmented the benchmark field quantification of these effects (1, 3, 4, 28, 36, 48-51).4.3.3 Additional Validation Work for Dosimetry Detectors: 4.3.3.1 Establishment of nuclear data, photo-reaction cross sections, and neutron damage reference files.4.3.3.2 Establishment of proper quality assurance procedures for sensor set designs and individual detectors.4.3.3.3 Interlaboratory comparisons using standard and reference neutron fields and other test reactors that provide adequate validations and calibrations, see Guide E2005.4.4 Reactor Physics Analysis and Interpretation (1, 3, 5, 11, 28, 35, 36, 39, 52)—When properly implemented, validated, and calibrated by vendor/utility groups, state-of-the-art reactor physics practices exist that are adequate for in- and ex-vessel estimates of PV-steel changes in fracture toughness for existing and future power plant surveillance programs.4.4.1 Required Accuracies and Benchmark Field Referencing: 4.4.1.1 The accuracies desirable for LWR-PV steel (surveillance capsule specimens and vessels) exposure definition are of the order of ±10 to 15 % (1σ). Under ideal conditions benchmarking computational techniques are capable of predicting absolute in- and ex-vessel neutron exposures and reaction rates per unit reactor core power to within ±15 % (but generally not to within ±5 %). The accuracy will be worse, however, in applications to actual power plants because of geometrical and other complexities (1, 3, 4, 11, 21, 36-39, 52).4.4.1.2 Calculated in-and ex-vessel neutron and gamma ray fields can be normalized to the core power history or to experimental measurements. The latter may include dosimetry from surveillance capsules, other in-vessel locations, or ex-vessel measurements in the cavity outside the vessel. In each case, the uncertainty arising from the calculation needs to be considered.4.4.2 Power Plant Reactor Physics Analysis and Interpretation: 4.4.2.1 Result of Neglect of Benchmarking—One quarter thickness location (1/4T) vessel wall estimates of damage exposure are not easily compared with experimental results. “Lead factors,” based on the different ways they can be calculated (fluence >0.1 or >1.0 MeV and dpa) may not always be conservative; that is, some surveillance capsules have been positioned in-vessel such that the actual lead factor is very near unity—no lead at all. Also the differences between lead factors based on fluence E > 0.1 or > 1 MeV and dpa can be significant, perhaps 50 % or more (1, 11, 21, 28, 36-38, 52).4.4.3 PCA, VENUS, and NESDIP Experiments and PCA Blind Test: 4.4.3.1 Test of transport theory methods under clean geometry and clean core source conditions shall be made (1, 4, 11, 52).4.4.3.2 This is a necessary but not sufficient benchmark test of the adequacy of a vendor/utility group’s power reactor physics computational tools.4.4.3.3 The standard recommendation should be that the vendor/utility group’s observed differences between their own calculated and the PCA, VENUS, and NESDIP measured integral and differential exposure and reaction rate parameters be used to validate and improve their calculational tools (if the differences fall outside the PCA, VENUS, and NESDIP experimental accuracy limits).4.4.4 PWR and BWR Generic Power Reactor Tests: 4.4.4.1 Test of transport theory methods under actual geometry and variable core source conditions (1, 3, 4, 28, 35, 36, 53).4.4.4.2 This is a necessary and partly sufficient benchmark test of the adequacy of a vendor/utility group’s power reactor physics computational tools.4.4.4.3 The standard recommendation should be that the vendor/utility group’s observed differences between their own calculated and the selected PWR or BWR measured integral and differential exposure and reaction rate parameters be used to validate and improve their calculation tools (if the differences fall outside of the selected PWR or BWR experimental accuracy limits).4.4.4.4 The power reactor “benchmarks” that have been established for this purpose are identified and discussed in Refs (1, 3, 4, 35, 53) and their references and in Guide E2006.4.4.5 Operating Power Reactor Tests: 4.4.5.1 This is a necessary test of transport theory methods under actual geometry and variable core source conditions, but for a particular type or class of vendor/utility group power reactors. Here, actual in-vessel surveillance capsule and any required ex-vessel measured dosimetry information will be utilized as in 4.4.4 (1, 3, 4, 28, 35, 36, 53). Note, however, that operating power reactor tests are not sufficient by themselves (Reg. Guide 1.190, Section 4.4.5.1).4.4.5.2 Accuracies associated with surveillance program reported values of exposures and reaction rates are expected to be in the 10 to 30 % (1σ) range (36).4.5 Metallurgical Damage Correlation Analysis and Interpretation (1-8, 10, 11, 13, 15-29, 36-38)—When properly implemented, validated, and calibrated by vendor/utility groups, state-of-the-art metallurgical damage correlation practices exist that are adequate for in- and ex-vessel estimates of PV-steel changes in fracture toughness for existing and future power plant surveillance programs.4.5.1 Required Accuracies and Benchmark Field Referencing: 4.5.1.1 The accuracies desirable and achievable for LWR-PV steel (test reactor specimens, surveillance capsule specimens, and vessels and support structure) data correlation and data extrapolation (to predict fracture toughness changes both in space and time) are of the order of ±10 to 30 % (1σ). In order to achieve such a goal, however, the metallurgical parameters (ΔNDTT, upper shelf, yield strength, etc.) must be interpretable to well within ±20 to 30 % (1σ). This mandates that in addition to the dosimetry and physics variables already discussed that the individual uncertainties and errors associated with a number of other variables (neutron dose rate, neutron spectrum, irradiation temperature, steel chemical composition, and microstructure) must be minimized and results must be interpretable to within the same ±10 to 30 % (1σ) range.4.5.1.2 Advanced sensor sets (including dosimetry, temperature and damage correlation sensors) and practices have been established in support of the above for use by vendor/utility groups (1, 4, 5, 11, 39, 50, 54, 55).4.5.1.3 Benchmark field referencing of utilities' vendor/service laboratories, as well as advanced practices, is in progress or being planned that is (1, 3-6, 28, 50, 54-56):(1) Needed for validation of data correlation procedures and time and space extrapolations (to PV positions: surface, 1/4 T, etc.) of test reactor and power reactor surveillance capsule metallurgical and neutron exposure data.(2) Being or will be tested in test reactor neutron fields to quantify and minimize uncertainties and errors (included here is the use of damage correlation materials—steel, sapphire, etc.).4.5.2 Benchmark Field Referencing—The PSF (all positions: surveillance, surface, 1/4T, 1/2T, and the void box) together with the Melusine PV-simulator and other tests, such as for thermal neutron effects, provide needed validation data on all variables—dosimetry, physics, and metallurgy (1, 4, 10, 19, 21, 22, 37, 38). Other test reactor data comes from surveillance capsule results that have been benchmarked by vendor/service laboratory/utility groups (1, 3, 4, 6, 11, 18, 27, 28, 36, 40-44, 47).4.5.3 Reg. Guide 1.99, NRC, EPRI Databases—NRC and Electric Power Research Institute (EPRI) databases have been studied on an ongoing basis by ASTM Subcommittees E10.02 and E10.05, vendors, utilities, EPRI, and NRC contractors to establish improved databases for existing test and power reactor measured property change data. ASTM task groups recommend the use of updated and new exposure units (fluence total >0.1, >1.0 MeV, and dpa) for the NRC and EPRI databases (1, 2, 6, 7, 13, 18, 27, 36, 40-44, 47), and incorporate these recommendations in the appropriate standards. ASTM subcommittee E10.02 has updated the embrittlement database and the prediction model in E900–15. The exposure unit used is total fluence for E > 1 MeV. The basis of the prediction model is documented in an adjunct associated with E900, available from ASTM.4 The success of this effort depends on good cooperation between research and individual service laboratories and vendor/utility groups. An ASTM dosimetry cross section file based on the latest evaluations, as detailed in Guide E1018, and incorporating corrections for all known variables (perturbations, photo-reactions, spectrum, burn-in, yields, fluence time history, etc.) will be used as required and justified. Test reactor data will be addressed in a similar manner, as appropriate.1.1 This master matrix standard describes a series of standard practices, guides, and methods for the prediction of neutron-induced changes in light-water reactor (LWR) pressure vessel (PV) and support structure steels throughout a pressure vessel’s service life (Fig. 1). Referenced documents are listed in Section 2. The summary information that is provided in Sections 3 and 4 is essential for establishing proper understanding and communications between the writers and users of this set of matrix standards. It was extracted from the referenced standards (Section 2) and references for use by individual writers and users. More detailed writers’ and users’ information, justification, and specific requirements for the individual practices, guides, and methods are provided in Sections 3 – 5. General requirements of content and consistency are discussed in Section 6.FIG. 1 Organization and Use of ASTM Standards in the E706 Master Matrix1.2 This master matrix is intended as a reference and guide to the preparation, revision, and use of standards in the series.1.3 To account for neutron radiation damage in setting pressure-temperature limits and making fracture analyses ((1-12)2 and Guide E509), neutron-induced changes in reactor pressure vessel steel fracture toughness must be predicted, then checked by extrapolation of surveillance program data during a vessel’s service life. Uncertainties in the predicting methodology can be significant. Techniques, variables, and uncertainties associated with the physical measurements of PV and support structure steel property changes are not considered in this master matrix, but elsewhere ((2, 6, 7, 11-26) and Guide E509).1.4 The techniques, variables, and uncertainties related to (1) neutron and gamma dosimetry, (2) physics (neutronics and gamma effects), and (3) metallurgical damage correlation procedures and data are addressed in separate standards belonging to this master matrix (1, 17). The main variables of concern to (1), (2), and (3) are as follows:1.4.1 Steel chemical composition and microstructure,1.4.2 Steel irradiation temperature,1.4.3 Power plant configurations and dimensions, from the core periphery to surveillance positions and into the vessel and cavity walls,1.4.4 Core power distribution,1.4.5 Reactor operating history,1.4.6 Reactor physics computations,1.4.7 Selection of neutron exposure units,1.4.8 Dosimetry measurements,1.4.9 Neutron special effects, and1.4.10 Neutron dose rate effects.1.5 A number of methods and standards exist for ensuring the adequacy of fracture control of reactor pressure vessel belt lines under normal and accident loads ((1, 7, 8, 11, 12, 14, 16, 17, 23-27), Referenced Documents: ASTM Standards (2.1), Nuclear Regulatory Documents (2.3) and ASME Standards (2.4)). As older LWR pressure vessels become more highly irradiated, the predictive capability for changes in toughness must improve. Since during a vessel's service life an increasing amount of information will be available from test reactor and power reactor surveillance programs, procedures to evaluate and use this information must be used (1, 2, 4-9, 11, 12, 23-26, 28). This master matrix defines the current (1) scope, (2) areas of application, and (3) general grouping for the series of ASTM standards, as shown in Fig. 1.1.6 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.

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1.1 This specification covers gray iron for castings suitable for pressure-containing parts for use at temperatures up to 350°C.1.2 Castings of all classes are suitable for use up to 230°C. For temperatures above 230°C and up to 350°C, only Class 275, 300, 325, 350, 380, and 415 castings are suitable.1.3 This specification is the SI companion to Specification A278.

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5.1 This test method is a standard procedure for determining the air leakage characteristics under specified air pressure differences at ambient conditions.NOTE 2: The air pressure differences acting across a building envelope vary greatly. The factors affecting air pressure differences and the implications or the resulting air leakage relative to the environment within buildings are discussed in the literature.4-6 These factors should be fully considered in specifying the test pressure differences to be used.5.2 Rates of air leakage are sometimes used for comparison purposes. Such comparisons may not be valid unless the components being tested and compared are of essentially the same size, configuration, and design.1.1 This test method covers a standard laboratory procedure for determining the air leakage rates of exterior windows, skylights, curtain walls, and doors under specified differential pressure conditions across the specimen. The test method described is for tests with constant temperature and humidity across the specimen. Persons interested in performing air leakage tests on units exposed to various temperature differences across the specimen should reference Test Method E1424.1.2 This laboratory procedure is applicable to exterior windows, skylights, curtain walls, and doors and is intended to measure only such leakage associated with the assembly and not the installation. The test method can be adapted for the latter purpose.NOTE 1: Performing tests under uncontrolled conditions or with a temperature differential across the specimen may affect the air leakage rate. This is not addressed by this test method.1.3 This test method is intended for laboratory use. Persons interested in performing field air leakage tests on installed units should reference Test Method E783.1.4 Persons interested in evaluating air permeance of building materials should reference Test Method E2178.1.5 Persons interested in determining air leakage of air barrier assemblies should reference Test Method E2357.1.6 Persons using this procedure should be knowledgeable in the areas of fluid mechanics, instrumentation practices, and shall have a general understanding of fenestration products and components.1.7 The values stated in either SI units or inch-pound units are to be regarded separately as standard. The values stated in each system are not necessarily exact equivalents; therefore, to ensure conformance with the standard, each system shall be used independently of the other, and values from the two systems shall not be combined.1.8 This standard does not purport to address all of the safety problems, 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. For specific hazard statement, see Section 7.1.9 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.

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