5.1 Uranium dioxide is used as a nuclear-reactor fuel. Gadolinium oxide is used as an additive to uranium dioxide. In order to be suitable for this purpose, these materials must meet certain criteria for impurity content. This test method is designed to determine whether the carbon content meets Specifications C753, C776, C888, and C922.1.1 This test method covers the determination of carbon in nuclear-grade uranium oxide powders and pellets to determine compliance with specifications.1.2 Gadolinium oxide (Gd2O3) and gadolinium oxide-uranium oxide powders and pellets may also be analyzed using this test method.1.3 This test method covers the determination of 5 to 500 μg of residual carbon.1.4 This test method describes an induction furnace carrier gas combustion system equipped with an infrared detector. It may also be applied to a similar instrument equipped with a thermal conductivity detector.1.5 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.5.1 The preferred system of units is micrograms carbon per gram of sample (μg/g sample) or micrograms carbon per gram of uranium (μg/g U).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 and health practices and determine the applicability of regulatory limitations prior to use.

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This specification covers finished pellets composed of sintered gadolinium oxide-uranium dioxide of any concentration for use in light-water reactors. Materials shall adhere to specified chemical (impurity content, stoichiometry, moisture content, and gadolinium oxide concentration), nuclear (isotopic content), and physical (dimensions, density, homogeneity, integrity, axial and circumferential surface cracks, cylindrical surface chips, pellets ends, cleanliness and workmanship, identification, and irradiation stability) requirements.1.1 This specification is for finished sintered (U,Gd)O2 pellets. It applies to (U,Gd)O2 pellets containing uranium (U) of any 235U concentration and any concentration of gadolinium oxide (Gd2O3) for use in nuclear reactors.1.2 This specification recognizes the presence of reprocessed U in the fuel cycle and consequently defines isotopic limits for (U,Gd)O2 pellets made from commercial grade UO2. Such commercial grade UO2 is defined so that, regarding fuel design and manufacture, the product is essentially equivalent to that made from unirradiated U. UO2 falling outside these limits cannot necessarily be regarded as equivalent and may thus need special provisions at the fuel fabrication plant or in the fuel design.1.3 This specification does not include (a) provisions for preventing criticality accidents, (b) requirements for health and safety, (c) avoidance of hazards, or (d) shipping precautions and controls. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all applicable international, federal, state, and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material. Examples of U.S. Governmental documents are Code of Federal Regulations (Latest Edition), Title 10, Part 50, Title 10, Part 70, Title 10, Part 71, and Title 49, Part 173.1.4 Units—The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.5 The following precautionary caveat pertains only to the technical requirements portion, Section 4, 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.1.6 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.

定价： 515元 / 折扣价： 438 元 加购物车

定价： 843元 / 折扣价： 717 元 加购物车

定价： 590元 / 折扣价： 502 元 加购物车

4.1 Before proceeding with this test method, refer to the specification of the material being tested. Any test specimen preparation, conditioning, dimensions, or testing parameters, or a combination thereof, covered in the materials specification shall take precedence over those mentioned in this test method. If there are no material specifications, then default conditions apply.NOTE 2: Some materials, such as polyamide (nylon), can be cooled very differently during the production of the pellets. This variation in the cooling of the pellets can result in different levels of crystallinity in the pellets only. More crystalline nylons will be more opaque than amorphous nylons. This will result in differences in pellet opacity. The pellet shape is independent of the crystallinity of the material. This variation in pellet appearance, due to varying levels of crystallinity, does not affect final properties.NOTE 3: This test method should not be used for general material specifications.4.2 This test method describes a technique useful for making color comparisons of resins in pellet form that is fast and convenient as it does not require preparation, such as molding or extruding specimens. The test method shall be used only to compare specimens of similar pellet shape, size, texture, and degree of translucency. For example, compare translucent disc-shaped pellets to translucent disc-shaped pellets, not with opaque, rectangular shaped pellets.4.3 Exact measurements of resin pellet color are not necessarily directly related to the color of the final cast, molded or extruded product due to the multitude of variables, such as producing variables, methods, and pellet shape and size. Color measurements can be useful for comparing resins in pellet form when all samples are similar in shape and size.4.4 A three-number tristimulus system is necessary to quantify color completely and precisely. The general method used in this procedure measures color using the CIE Systems described in Practice E308, Test Method D2244, the CIE 1976 (X, Y, Z) system, and, the CIELAB 1976 color space.34.5 Individual components of the tristimulus measurement such as CIE Y (Luminance), Hunter L, a, b, or CIE L*, a*, b* values or other useful metrics like yellowness index in accordance with Practice E313 can be used to describe color attributes of materials.1.1 This test method is used for the instrumental measurement of the degree of yellowness (or change of degree of yellowness) under daylight illumination of homogeneous, nonfluorescent, nearly-colorless transparent or nearly-white translucent or opaque plastics. The measurement is made on pellets and based on tristimulus values obtained with a spectrophotometer or colorimeter.1.2 This test method is applicable to the color analysis of plastic pellets. It is possible that each material will have unique characteristics that determine the color values.1.3 This procedure outlines a method to determine color measurements, such as Yellowness Index (YI), CIE X, Y, Z, and Hunter L, a, b, or CIE L*, a*, b*.1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.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.NOTE 1: This standard and ISO 17223 address the same subject matter but differ in technical content.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.

定价： 590元 / 折扣价： 502 元 加购物车

定价： 590元 / 折扣价： 502 元 加购物车

5.1 Uranium dioxide is used as a nuclear-reactor fuel. This test method is designed to determine whether the percent uranium and O/U or O/M content meet Specifications C776 and C922.1.1 This test method applies to the determination of uranium, the oxygen to uranium (O/U) ratio in sintered uranium dioxide pellets, and the oxygen to metal (O/M) ratio in sintered gadolinium oxide-uranium dioxide pellets with a Gd2O3 concentration of up to 12 weight %. The O/M calculations assume that the gadolinium and uranium oxides are present in a metal dioxide solid solution.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. For specific hazards statements, see Section 9.1.4 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

定价： 515元 / 折扣价： 438 元 加购物车

5.1 The test method is designed to show whether or not a material meets the specifications as given in Specifications C753 or C776.5.2 The powder’s stoichiometry is useful for predicting the oxide's sintering behavior in the pellet production process.1.1 This test method covers the determination of uranium and the oxygen to uranium atomic ratio in nuclear grade uranium dioxide powder and pellets.1.2 This test method does not include provisions for preventing criticality accidents or requirements for health and safety. Observance of this test method does not relieve the user of the obligation to be aware of and conform to all international, national, or federal, state and local regulations pertaining to possessing, shipping, processing, or using source or special nuclear material.1.3 This test method also is applicable to UO3 and U3O8 powder.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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5.1 This test method is applicable to samples containing 1 to 10 % gadolinium oxide and 90 to 99 % uranium oxide on the “as received” basis. The method may be used to determine concentration of either uranium, gadolinium, or both.5.2 Either wavelength-dispersive or energy-dispersive X-ray fluorescence systems may be used provided the software accompanying the system is able to accommodate the use of internal standards.1.1 This test method describes the steps necessary for the preparation and analysis by X-ray fluorescence (XRF) of gadolinium or uranium (or both) in gadolinium oxide-uranium oxide pellets or powders.1.2 This test method requires the use of appropriate internal standard(s). Care must be taken to ascertain that samples analyzed by this method do not contain the internal standard element(s) or that this contamination has been corrected for mathematically whenever present. Such corrections are not addressed in this test method.1.3 This standard contains notes that are explanatory and are not part of the mandatory requirements of the standard.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. Specific precautions are given in Section 8 and various notes throughout the method.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.

定价： 515元 / 折扣价： 438 元 加购物车

5.1 Uranium dioxide is used as a nuclear-reactor fuel. Gadolinium oxide is used as an additive to uranium dioxide. In order to be suitable for this purpose, these materials must meet certain criteria for impurity content. This test method is designed to determine whether the hydrogen content meets Specifications C753, C776, C888, and C922.1.1 This test method applies to the determination of hydrogen in nuclear-grade uranium oxide powders and pellets to determine compliance with specifications. Gadolinium oxide (Gd2O3) and gadolinium oxide-uranium oxide powders and pellets may also be analyzed using this test method.1.2 This standard describes a procedure for measuring the total hydrogen content of uranium oxides. The total hydrogen content results from absorbed water, water of crystallization, hydro-carbides and other hydrogenated compounds which may exist as fuel's impurities.1.3 This test method covers the determination of 0.05 to 200 μg of residual hydrogen.1.4 This test method describes an electrode furnace carrier gas combustion system equipped with a thermal conductivity detector.1.5 The preferred system of units is micrograms hydrogen per gram of sample (μg/g sample) or micrograms hydrogen per gram of uranium (μg/g U).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. For specific hazard statements, see Section 9.1.8 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： 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： 515元 / 折扣价： 438 元 加购物车

4.1 Aluminum oxide pellets are used in a reactor core as filler or spacers within fuel, burnable poison, or control rods. In order to be suitable for this purpose, the material must meet certain criteria for impurity content. These test methods are designed to show whether or not a given material meets the specifications for these items as described in Specification C785.4.1.1 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.4.2 Aluminum oxide-boron carbide composite pellets are used in a reactor core as a component in neutron absorber rods. In order to be suitable for this purpose, the material must meet certain criteria for boron content, isotopic composition, and impurity content as described in Specification C784.4.2.1 The material is assayed for boron to determine whether the boron content is as specified by the purchaser.4.2.2 Determination of the isotopic content of the boron is made to establish whether the 10B concentration is in compliance with the purchaser's specifications.4.2.3 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded.1.1 These test methods cover procedures for the chemical, mass spectrometric, and spectrochemical analysis of nuclear-grade aluminum oxide and aluminum oxide-boron carbide composite pellets to determine compliance with specifications.1.2 The analytical procedures appear in the following order:  Sections Boron by Titrimetry and ICP OES  8 to 17Separation of Boron for Mass Spectrometry 18 to 23Isotopic Composition by Mass Spectrometry 24 to 27Separation of Halides by Pyrohydrolysis 28 to 31Chloride and Fluoride by Ion-Selective Electrode 32 to 34Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 35 to 37Trace Elements by Emission Spectroscopy 38 to 50Keywords 511.3 The values stated in SI units are to be regarded as the standard.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. (For specific precautionary statements, see Section 6.)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 ceramographic examination of the nuclear fuel pellet is mandatory to ensure that the microstructural characteristics are in compliance with the fuel specifications relative to performance in reactor, particularly concerning thermo-mechanical behavior and fission gas release.5.2 This practice is applicable for sintered UO2 pellets with any 235U concentration and (U,Pu)O2 pellets containing up to 15 weight % PuO2 with less than 10 % porosity.1.1 This practice describes the procedure for preparing nuclear-grade uranium dioxide (UO2) or mixed uranium-plutonium dioxide (MOX or (U,Pu)O2)), sintered and non-irradiated pellets for subsequent microstructural analysis (hereafter referred to as ceramographic examination).1.2 The ceramographic examination is performed to confirm that the microstructure of the sintered pellet is in compliance with the fuel specification, for example as defined in Specifications C776 and C833, as a function of the initial raw material properties and manufacturing process parameters.1.3 The microstructure of a ceramic pellet includes: grain size, porosity size and distribution, and phase distribution for (U,Pu)O2 pellets, that is, Pu-rich cluster size and distribution.21.4 The microstructural characteristics of the pellet are accessible after preparation which involves: sawing, mounting in a resin, surface polishing, and chemical etching, thermal etching, or both.1.5 This practice describes the preparation processes mentioned in 1.4; it does not discuss the associated sampling practices (for example, Practice E105) or ceramographic examination methods (for example, the methods for determining average grain size are covered in Test Method E112).1.6 Due to the radiotoxicity associated with these nuclear materials, all operations described in this practice should be performed in glovebox for (U,Pu)O2 pellets and in a hood for UO2 pellets.1.7 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this standard.1.8 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.1.9 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.

定价： 590元 / 折扣价： 502 元 加购物车