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5.1 The crushing strength aids the pellet producer in the determination of quality problems associated with the production of pellets.5.2 The crushing strength is often used by the pellet consumer as a quality indicator for performance in the blast furnace and gas-based direct reduction plants.1.1 This test method describes a method for determining the crushing strength of fired iron ore pellets and direct-reduced iron. Cylindrical agglomerates and briquettes are not covered by this test method.1.2 The values as stated in SI units are to be regarded as the standards. The values in parentheses are given for information only.1.3 Results given by this test should be similar to those from ISO 4700 (see Appendix X1 for details).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.

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ASTM C967-20 Standard Specification for Uranium Ore Concentrate Active 发布日期 :  1970-01-01 实施日期 : 

This specification covers uranium ore concentrate. Chemical composition shall have a minimum content requirement for uranium and a limited content for uranium isotope, insoluble uranium, extractable organic, and impurities. Uranium ore shall also conform to chemical analyses, particle size, flow ability, and foreign matter contents according to the specification. Standard packaging requirements for uranium ore shall also be met according to the specification.1.1 This specification covers uranium ore concentrate containing a minimum of 65 mass % uranium.1.2 This specification does not include requirements for health and safety. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, national, state, and local regulations pertaining to possessing, shipping, or using source nuclear material (see 2.2).1.3 The values stated in SI units are to be regarded as standard. The values given in parentheses after SI units are provided for information only and are not considered 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.

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This practice sets guidelines for the receiving, testing and reporting of result of the investigation of metal, ores and related materials that may constitute evidence that is or may become involved in litigation. It outlines procedures to be followed to document the nature and condition of the evidence, the planning and performance of the testing, and actions that involve altering the nature or condition of the evidence.1.1 This practice covers the procedures to be used for receiving, testing and reporting results of investigation of metals, ores, related materials or samples thereof that have been the subject of an incident that is or is reasonably expected to be the subject of litigation.1.2 This practice was developed particularly for cases involving civil litigation, however it can be applied to criminal cases where it does not conflict with applicable laws and regulations.

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4.1 The test methods in this standard are designed to show whether a given material meets the specifications prescribed in Specification C967.4.2 Because of the variability of matrices of uranium-ore concentrate and the limited availability of suitable reference or calibration materials, the precision and bias of these test methods should be established by each individual laboratory that will use them. The precision and bias statements given for each test method are those reported by various laboratories and can be used as a guideline.4.3 Instrumental test methods such as X-ray fluorescence and emission spectroscopy can be used for the determination of some impurities where such equipment is available.1.1 These test methods cover procedures for the chemical and atomic absorption analysis of uranium-ore concentrates to determine compliance with the requirements prescribed in Specification C967.1.2 The analytical procedures appear in the following order:  SectionsUranium by Ferrous Sulfate Reduction—Potassium Dichromate  Titrimetry    9Nitric Acid-Insoluble Uranium  10 to 18Extractable Organic Material  19 to 26Determination of Arsenic  27Carbonate by CO2 Gravimetry  28 to 34Fluoride by Ion-Selective Electrode  35 to 42Halides by Volhard Titration  43 to 50Phosphorus by Spectrophotometry  52 to 60Determination of Silicon  61Determination of Thorium  62Calcium, Iron, Magnesium, Molybdenum, Titanium, and Vana- dium by Atomic Absorption Spectrophotometry  63 to 72Potassium and Sodium by Atomic Absorption  Spectrophotometry  73 to 82Boron by Spectrophotometry 83 to 921.3 The values stated in SI units are to be regarded as standard. The values given in parentheses are for information only.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. A specific precautionary statement is given in Section 7.1.5 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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5.1 The test method within this standard is used to demonstrate uranium ore-concentrate material meets the moisture specification defined in Specification C967 or other applicable requirements.1.1 This test method is used to determine compliance with Specification C967 for the requirements of moisture in uranium ore concentrates (UOC). A procedure is given to determine the approximate temperature for drying the UOC; normally 110 °C but possibly 165 °C for uranyl peroxides. The dried uranium ore-concentrate resulting from this procedure is then used for performing additional analyses described in Specification C967.1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are mathematical equivalents that are provided for information only and are not considered 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.

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5.1 This test method is a comparative method intended primarily to test materials for compliance with compositional specifications or for monitoring. It is assumed that all who use these procedures will be trained analysts capable of performing common laboratory procedures skillfully and safely. It is expected that work will be performed in a properly equipped laboratory and that proper waste disposal procedures will be followed. Appropriate quality control practices must be followed such as those described in Guide E882.5.2 This test method is used to monitor the feed to blast furnaces and gas-based direct reduction plants for process control.1.1 This test method covers a relative measure of the resistance of iron ore pellets, lump, and sinter to degradation by impact and by abrasion.1.2 The values stated in SI units are to be regarded as standard. The values given in parentheses are mathematical conversions to inch-pound units that are provided for information only and are not considered standard.1.3 Results given by this test method should be similar to those from ISO 3271 (see Appendix X1 for details).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.

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ASTM C1075-17(2022) Standard Practices for Sampling Uranium-Ore Concentrate Active 发布日期 :  1970-01-01 实施日期 : 

AbstractThese practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) and for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples. These practices consist of a number of alternative procedures for (1) primary sampling such as one-stage falling stream, two-stage falling stream, and Auger sampling; (2) secondary sampling such as straight-path (reciprocating) cutter sampling and rotating (Vezin) cutter multi-sampling; (3) sample preparation such as concurrent-drying, natural moisture, and calcination; and (4) sample packaging such as wax sealing and vacuum sealing. These procedures do not include requirements for health, safety, and accountability. The material and sampling equipment requirements are detailed. Schematic diagrams of the primary and secondary samplers are provided.1.1 These practices are intended to provide the nuclear industry with procedures for obtaining representative bulk samples from uranium-ore concentrates (UOC) (see Specification C967).1.2 These practices also provide for obtaining a series of representative secondary samples from the original bulk sample for the determination of moisture and other test purposes, and for the preparation of pulverized analytical samples (see Test Methods C1022 and C1843).1.3 These practices consist of a number of alternative procedures for sampling and sample preparation which have been shown to be satisfactory through long experience in the nuclear industry. These procedures are described in the following order.Stage Procedure Section     Primary Sampling One-stage falling stream 5  Two-stage falling stream 6  Auger 7Secondary Sampling Straight-path (reciprocating) 8  Rotating (Vezin) 9, 101.3.1 The primary and secondary sampling stages can be organized in the following way:1.3.2 It is possible to combine the various elements of these stages in different ways to give satisfactory results depending on the agreed requirements of the contracting parties. For a given stage, however, each procedure must be regarded as a whole. It is highly inadvisable to mix elements belonging to different procedures.1.4 These procedures do not include requirements for health, safety, and accountability. The observance of these practices does not relieve the user of the obligation to be aware of and to conform to all applicable international, federal, state, and local regulations pertaining to processing, shipping, or using uranium-ore concentrates. (Guidance is provided in CFR 10, Chapter 1.)1.5 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.1.6 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.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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