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AS 1562.1:2018 Design and installation of sheet roof and wall cladding Metal 现行 发布日期 :  2018-03-01 实施日期 : 

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16.1 For the purpose of determining compliance with the specified limits of property requirements, an observed value or a calculated value shall be rounded in accordance with the rounding method of Practice E29.Test Rounded Units for Observedor Calculated Value Chemical composition, tolerance (when expressed in decimals) nearest unit in the last right hand place   of figures of the specified limitTensile strength and yield strength nearest 1000 psi (10 MPa)Elongation nearest 1 %AbstractThis specification covers the standard requirements for wrought zirconium and zirconium alloy seamless and welded tubes for nuclear applications except for nuclear fuel cladding. Five grades of reactor grade zirconium and zirconium alloys with R60001, R60802, R60804, R60901, and R60904 UNS number designations are described. Material shall be made from ingots produced by vacuum arc melting, electron beam melting, or other melting process to be carried out in furnaces conventionally used for reactive metals. Seamless tubes may be made by billet extrusion with subsequent cold working, by drawing, swaging, or rocking, with intermediate annealing. Welded tubing shall be made from flat-rolled products by an automatic or semiautomatic welding process with no addition of filler metal and shall be cold reduced by drawing, swaging, or rocking. The products shall be in the recrystallized or cold-worked and stress-relieved conditions and shall be furnished by as-cold reducing, pickling, grounding, polishing, or end-saw cutting, machining, or shearing. Chemical and product analysis shall be performed on the materials which shall meet the chemical composition requirements for tin, iron, chromium, nickel, niobium, oxygen, and other impurity elements. The tensile properties shall be determined by a tensile test method and shall conform to the tensile strength, yield strength, and elongation limits. Steam and water corrosion tests and hydrostatic test shall be conducted to determine the acceptance criteria for corrosion and internal hydrostatic pressure, respectively. Burst properties, contractile strain ratio, grain size, and hydride orientation of the finished tubing shall also be determined.1.1 This specification covers seamless and welded wrought zirconium and zirconium-alloy tubes for nuclear application. Nuclear fuel cladding is covered in Specification B811.1.2 Five grades of reactor grade zirconium and zirconium alloys suitable for nuclear application are described.1.2.1 The present UNS numbers designated for the five grades are given in Table 1.1.3 Unless a single unit is used, for example corrosion mass gain in mg/dm2, the values stated in either inch-pound or SI units are to be regarded separately as standard. The values stated in each system are not exact equivalents; therefore each system must be used independently of the other. SI values cannot be mixed with inch-pound values.1.4 The following precautionary caveat pertains only to the test method portions 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 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.

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The physical and mechanical properties of cladding materials can be altered by exposure to a high-energy neutron flux. The magnitude and relationship of these changes are functions of the material and its metallurgical condition; the amount, rate, and energy spectrum of the radiation; the exposure temperature; the test temperature; the purity, velocity, volume, and purification system of the coolant; and effects of contained fuel.1.1 This practice covers the procedures for postirradiation examination of cladding, determination of breached nuclear fuel elements, selection of material and tests for radiation studies, determination of radiation conditions, conduction of tests for mechanical properties of cladding, and the reporting of data.1.2 The purpose of this practice is to provide detailed guidelines for the postirradiation examination of fuel element cladding and to achieve better correlation and interpretation of the data in the field of radiation effects.1.3 This practice may be applied to metallic cladding from all types of fuel elements. The tests described in this practice for determining mechanical properties of the fuel element cladding practice should be included in the preirradiation characterization of the cladding and for planning irradiation effects tests for evaluation of materials for cladding and other components in nuclear reactors.Note 1—The values stated in SI units as described in Standard E 380 are to be regarded as the standard.

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5.1 This test method gives a standard procedure for determining structural performance under uniform static air pressure difference. This typically is intended to represent the effects of wind loads on exterior building surface elements. The actual loading on building surfaces is quite complex, varying with wind direction, time, height above ground, building shape, terrain, surrounding structures, and other factors. These factors are discussed in the literature in 2.2 and 2.3 and Footnotes 4 and 5.NOTE 1: In applying the results of tests by this test method, it should be borne in mind that the performance of a cladding system may be a function of fabrication, installation, and adjustment, and that the specimen may or may not truly represent the actual structure. In service, the performance will also depend on the rigidity of supporting construction and on the resistance of components to deterioration by various causes, to vibration, to thermal expansion and contraction, etc.1.1 This test method covers the determination of the structural performance of dimension stone cladding systems under positive and negative uniform static air pressure differences, using a test chamber.1.2 The proper use of this test method requires a knowledge of the principles of pressure and deflection measurement.1.3 This test method describes the apparatus and the procedure to be used for applying either specific test loads or unknown ultimate values of uniformity distributed test loads to a specimen.1.3.1 Procedure A (see 11.2) shall be used when deflections at maximum load only are required.1.3.2 Procedure B (see 11.3) shall be used when a load-deflection curve is required.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 non-conformance with the 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. For specific hazard statements, see Section 7.1.6 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 seamless wrought zirconium-alloy tubes for nuclear reactor fuel cladding application. Two grades of reactor grade zirconium alloys are described. Tubes covered by this specification shall be made from ingots produced by multiple vacuum arc or electron beam melting in furnaces of a type conventionally used for reactive materials. The tubes shall conform to the requirements for chemical composition prescribed. Recrsytallisation annealed tubes shall conform to the requirements for mechanical properties at room temperature prescribed. The tension test shall be conducted. Yield strength and tension properties shall be determined. Burst testing, when specified, shall be performed at room temperature on finished tubing.1.1 This specification covers seamless wrought zirconium-alloy tubes for nuclear fuel cladding application, in the outside diameter (OD) size range of 0.200 in. (5.1 mm) to 0.650 in. (16.5 mm) and wall thickness range of 0.010 in. (0.25 mm) to 0.035 in. (0.89 mm).1.2 Two grades of reactor grade zirconium alloys are described.1.2.1 The present UNS numbers designated for the two grades are given in Table 1.1.3 Unless a single unit is used, for example corrosion mass gain in mg/dm2, the values stated in either inch-pound or SI units are to be regarded separately as standard. The values stated in each system are not exact equivalents; therefore each system must be used independently of the other. SI values cannot be mixed with inch-pound values.1.4 The following precautionary caveat pertains only to the test method portions 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 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: 646元 / 折扣价: 550 加购物车

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