27.120.30 (Fissile materials and nuclear fuel tech 标准查询与下载

ASTM C1348-96 直接氢还原成核级二氧化铀用带低于5%的235U含量的混合氧化铀用标准规范

1.1 This specification covers blended uranium trioxide (UO3), U3O8, or mixtures of the two, powders that are intended for conversion into a sinterable uranium dioxide (UO2) powder by means of a direction reduction process. The UO2 powder product of the reduction process must meet the requirements of Specification C753 and be suitable for subsequent UO2 pellet fabrication by pressing and sintering methods. This specification applies to uranium oxides with a 235U enrichment less than 5 %. 1.2 This specification includes chemical, physical, and test method requirements for uranium oxide powders as they relate to the suitability of the powder for storage, transportation, and direct reduction of UO2 powder. This specification is applicable to uranium oxide powders for such use from any source. 1.3 The scope of this specification does not comprehensively cover all provisions for preventing criticality accidents, for health and safety, or for shipping. Observance of this specification does not relieve the user of the obligation to conform to all international, national, state, and local regulations for processing, shipping, or any other way of using uranium oxide powders (see 2.2 and 2.3). 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 The following safety hazards caveat pertains only to the test methods portion of the annexes in 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Specification for Blended Uranium Oxides with a ²³⁵U Content of Less Than 5 % for Direct Hydrogen Reduction to Nuclear Grade Uranium Dioxide

ASTM C761-96 六氟化铀的化学、质谱、核(放射性)及放射化学分析的标准试验方法

1.1 These test methods cover procedures for subsampling and for chemical, mass spectrometric, spectrochemical, nuclear, and radiochemical analysis of uranium hexafluoride (UF6). All of these test methods are in routine use to determine conformance to UF6 specifications in the Department of Energy (DOE) gaseous diffusion plants or at other DOE installations. 1.2 The analytical procedures in this document appear 1.3 Additional test methods have been developed and are included in Appendix X 1. 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 and health practices and determine the applicability of regulatory limitations prior to use. (For specific safeguard and safety consideration statements, see Section 6.)

Standard Test Methods for Chemical, Mass Spectrometric, Spectrochemical, Nuclear, and Radiochemical Analysis of Uranium Hexafluoride

ASTM C1030-95(2001) 用γ射线测试钚同位素成分的标准试验方法

1.1 This test method is applicable to the determination of isotopic abundances in isotopically homogeneous Pu-bearing materials. This test method may be applicable to other plutonium-bearing materials, some of which may require modifications to the described test method. 1.2 The procedure is applicable to sample sizes ranging from a few tenths of a gram up to the maximum sample weight allowed by criticality limits. 1.3 Because 242 Pu has no useful gamma-ray signature, its isotopic abundance is not determined. Isotopic correlation techniques may be used to estimate its relative abundance (Refs 1, 2). 1.4 This test method has been demonstrated in routine use for isotopic abundances ranging from 94 to 70% 239 Pu. This test method has also been employed for isotopic abundances outside this range. 1.5 The values stated in SI units are to be regarded as 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Determination of Plutonium Isotopic Composition by Gamma-Ray Spectrometry

ASTM C1296-95(2001) 用X射线荧光法（XRF）测定铀氧化物和硝酸铀酰溶液中硫的标准试验方法

1.1 This test method covers the sample preparation and analysis by X-ray fluorescence (XRF) of sulfur in uranium oxides and uranyl nitrate solutions. 1.2 This test method is valid for those solutions containing 100 to 500 181g sulfur/mL. Higher concentrations may be measured by appropriate dilutions. 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 and health practices and determine the applicability of regulatory limitations prior to use. See Section 9 and Note 1 for specific hazards statements.

Standard Test Method for Determination of Sulfur in Uranium Oxides and Uranyl Nitrate Solutions by X-Ray Fluorescence (XRF)

ASTM C1128-95e1 核燃料循环材料分析用操作参考材料制备的标准指南

1.1 This guide covers the preparation and characterization of working reference materials (WRM) that are produced by a laboratory for its own use in the analysis of nuclear materials. Guidance is provided for establishing traceability of WRMs to certified reference materials by a defined characterization process. The guidance provided is generic; it is not specific for a given material.1.2 The information provided by this guide is found in the following sections:SectionPlanning6Preparation7Packaging and Storage8Characterization9Statistical Analysis10Documentation 111.3 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Preparation of Working Reference Materials for Use in the Analysis of Nuclear Fuel Cycle Materials

ASTM C833-95a 烧结的二氧化铀、钚芯块标准规范

1.1 This specification covers finished sintered and ground (uranium-plutonium) dioxide pellets for use in thermal reactors. It applies to uranium-plutonium dioxide pellets containing plutonium additions up to 15 % weight. This specification may not completely cover the requirements for pellets fabricated from weapons-derived plutonium.1.2 This specification does not include ( 1) provisions for preventing criticality accidents or ( 2) 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, federal, state, and local regulations pertaining to possessing, processing, shipping, or using source or special nuclear material. Examples of U.S. government documents are Code of Federal Regulations Title 10, Part 50-Domestic Licensing of Production and Utilization Facilities; Title 10, Part 71-Packaging and Transportation of Radioactive Material; and Title 49, Part 173-General Requirements for Shipments and Packaging.1.3 The following safety hazards 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 and health practices and determine the applicability of regulatory limitations prior to use.1.4 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

Standard Specification for Sintered (Uranium-Plutonium) Dioxide Pellets

ASTM C1297-95e1 核燃料循环材料分析用实验室的定量分析法的标准导则

1.1 This guide covers the qualification of analysts to perform chemical analysis or physical measurements of nuclear fuel cycle materials. The guidance is general in that it is applicable to all analytical methods, but must be applied method by method. Also, the guidance is general in that it may be applied to initial qualification or requalification. 1.2 The guidance is provided in the following sections: Section Qualification Considerations 4 Demonstration Process 5 Statistical Tests 6 1.3 This standard does not apply to maintaining qualification during routine use of a method. Maintaining qualification is included in Guide C1210. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Guide for Qualification of Laboratory Analysts for the Analysis of Nuclear Fuel Cycle Materials

ASTM E402-95 用氧化镓载体技术作氧化铀(U308)光谱分析的标准试验方法

1.1 This test method covers the semiquantitative spectrographic analysis of high-purity U O for the 32 elements in the ranges indicated in Table 1. (Quantitative analyses of boron, chromium, iron, magnesium, manganese, nickel, and other impurities can be performed using densitometric methods.) 1.2 The test method can be applied to those samples of uranium and uranium compounds, or both, which can be converted to the black oxide (U O ) and which are of approximately 99.5% purity or better. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Spectrographic Analysis of Uranium Oxide (U₃O₈)by Gallium Oxide-Carrier Technique

ASTM C1307-95 用(III)钚数组分光光度法鉴定钚的标准测试方法

1.1 This test method describes the determination of total plutonium as plutonium(III) in nitrate and chloride solutions. The technique is applicable to solutions of plutonium dioxide powders and pellets (Test Methods C 697), nuclear grade mixed oxides (Test Methods C 698), plutonium metal (Test Methods C 758), and plutonium nitrate solutions (Test Methods C 759). Solid samples are dissolved using the appropriate dissolution techniques described in Practice C 1168. The use of this technique for other plutonium-bearing materials has been reported (1-5), but final determination of applicability must be made by the user. The applicable concentration range for plutonium sample solutions is 10-200 g Pu/L.1.2 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.

Standard Test Method for Plutonium Assay by Plutonium (III) Diode Array Spectrophotometry

ASTM C809-94(2000) 核纯级氧化铝和氧化铝.碳化硼复合球粒的化学分析,质谱分析和光谱化学分析的标准试验方法

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 7 to 13 Separation of Boron for Mass Spectrometry 14 to 19 Isotopic Composition by Mass Spectrometry 20 to 23 Separation of Halides by Pyrohydrolysis 24 to 27 Fluoride by Ion-Selective Electrode 28 to 30 Chloride, Bromide, and Iodide by Amperometric Microtitrimetry 31 to 33 Trace Elements by Emission Spectroscopy 34 to 46 1.3 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 and health practices and determine the applicability of regulatory limitations prior to use. (For specific precautionary statements, see Section 5.)

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and Aluminum Oxide-Boron Carbide Composite Pellets

ASTM C1268-94(2000) 用γ射线光谱法定量测定钚中镅241的标准试验方法

This test method allows the determination of americium 241 in a plutonium solution without separation of the americium from the plutonium. It is generally applicable to any solution containing americium 241. The americium 241 in solid plutonium materials may be determined when these materials are dissolved (see Practice C 1168). When the plutonium solution contains unacceptable levels of fission products or other materials, this method may be used following a tri-n-octylphosphine oxide (TOPO) extraction, ion exchange or other similar separation techniques (see Test Methods C 758 and C 759). This test method is less subject to interferences from plutonium than alpha counting since the energy of the gamma ray used for the analysis is better resolved from other gamma rays than the alpha particle energies used for alpha counting. The minimal sample preparation reduces the amount of sample handling and exposure to the analyst. This test method is applicable only to homogeneous solutions. This test method is not suitable for solutions containing solids. Solutions containing as little as 1 × 10 −5 g/L americium 241 may be analyzed using this method. The lower limit depends on the detector used and the counting geometry. Solutions containing high concentrations may be analyzed following an appropriate dilution.1.1 This test method covers the quantitative determination of americium 241 by gamma-ray spectrometry in plutonium nitrate solution samples that do not contain significant amounts of radioactive fission products or other high specific activity gamma-ray emitters. 1.2 This test method can be used to determine the americium 241 in samples of plutonium metal, oxide and other solid forms, when the solid is appropriately sampled and dissolved. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Quantitative Determination of Americium 241 in Plutonium by Gamma-Ray Spectrometry

ASTM C809-94(2007) 核纯级氧化铝和氧化铝-碳化硼复合丸状材料化学、质谱和光谱化学分析的标准试验方法

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 C 785. 3.1.1 Impurity content is determined to ensure that the maximum concentration limit of certain impurity elements is not exceeded. 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 C 784. 3.2.1 The material is assayed for boron to determine whether the boron content is as specified by the purchaser. 3.2.2 Determination of the isotopic content of the boron is made to establish whether the 10B concentration is in compliance with the purchaserrsquo;specifications. 3.2.3 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:1.3 The values stated in SI units are to be regarded as the standard.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. (For specific precautionary statements, see Section 5.)

Standard Test Methods for Chemical, Mass Spectrometric, and Spectrochemical Analysis of Nuclear-Grade Aluminum Oxide and AluminumOxide-Boron Carbide Composite Pellets

ASTM C1268-94(2008) 用伽马射线光谱法定量测定钚中镅241的标准试验方法

This test method allows the determination of americium 241 in a plutonium solution without separation of the americium from the plutonium. It is generally applicable to any solution containing americium 241. The americium 241 in solid plutonium materials may be determined when these materials are dissolved (see Practice C 1168). When the plutonium solution contains unacceptable levels of fission products or other materials, this method may be used following a tri-n-octylphosphine oxide (TOPO) extraction, ion exchange or other similar separation techniques (see Test Methods C 758 and C 759). This test method is less subject to interferences from plutonium than alpha counting since the energy of the gamma ray used for the analysis is better resolved from other gamma rays than the alpha particle energies used for alpha counting. The minimal sample preparation reduces the amount of sample handling and exposure to the analyst. This test method is applicable only to homogeneous solutions. This test method is not suitable for solutions containing solids. Solutions containing as little as 1 × 10 −5 g/L americium 241 may be analyzed using this method. The lower limit depends on the detector used and the counting geometry. Solutions containing high concentrations may be analyzed following an appropriate dilution.1.1 This test method covers the quantitative determination of americium 241 by gamma-ray spectrometry in plutonium nitrate solution samples that do not contain significant amounts of radioactive fission products or other high specific activity gamma-ray emitters. 1.2 This test method can be used to determine the americium 241 in samples of plutonium metal, oxide and other solid forms, when the solid is appropriately sampled and dissolved. 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Quantitative Determination of Americium 241 in Plutonium by Gamma-Ray Spectrometry

ASTM C785-93e1 核纯级的氧化铝丸标准规范

1.1 This specification applies to pellets of aluminum oxide that may be ultimately used in a reactor core design, for example, as filler or spacers within fuel, burnable poison, or control rods. In order to distinguish between the subject pellets and "burnable poison" pellets, it is established that the subject pellets are not intended to be used as neutron-absorbing material. 1.2 The values stated in SI units are to be regarded as the standard. The values given in parentheses are for information only.

Standard Specification for Nuclear-Grade Aluminum Oxide Pellets

ASTM C1022-93 铀精矿的化学分析和原子吸收分析的标准试验方法

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 C 967.1.2 The analytical procedures appear in the following order:SectionsUranium by Ferrous Sulfate Reduction-Potassium Dichromate Titrimetry9Nitric Acid-Insoluble Uranium10 to 18Extractable Organic Material19 to 26Arsenic by Diethyldithiocarbamate (Photometric Method)27 to 36Carbonate by CO2 Gravimetry37 to 43Fluoride by Ion-Selective Electrode44 to 51Halides by Volhard Titration52 to 59Moisture by Loss of Weight at 110176;C60 to 66Phosphorus by Spectrophotometry67 to 75Silicon by Gravimetry76 to 82Thorium by the Thorin (Photometric) Method83 to 91Calcium, Iron, Magnesium, Molybdenum, Titanium, and Vana-dium by Atomic Absorption Spectrophotometry92 to 101Potassium and Sodium by Atomic Absorption Spectrophotometry102 to 111Boron by Spectrophotometry112 to 1211.3 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 and health practices and determine the applicability of regulatory limitations prior to use. Specific precautionary statements are given in Sections 7, 32, and Note 14.

Standard Test Methods for Chemical and Atomic Absorption Analysis of Uranium-Ore Concentrate

ASTM D5411-93(2005)e1 反应堆冷却剂中放射性核素混合物每次蜕变的平均能量(E)计算的标准规范

1.1 This practice applies to the calculation of the average energy per disintegration (E) for a mixture of radionuclides in reactor coolant water.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, which are provided for information only and are not considered standard.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.

Standard Practice for Calculation of Average Energy Per Disintegration (E) for a Mixture of Radionuclides in Reactor Coolant

ASTM C1255-93(2005) 用能量色散X射线荧光光谱法分析土壤中铀和钍的标准试验方法

This test method was developed and the instrument calibrated using ground soils from the site of a nuclear materials plant. This test method can be used to measure the extent of contamination from uranium and thorium in ground soils. Since the detection limit of this technique (nominally 20 μg per gram) approaches typical background levels for these contaminants, the method can be used as a quick characterization of an on-site area to indicated points of contamination. Then after cleanup, EDXRF may be used to verify the elimination of contamination or other analysis methods (such as colorimetry, fluoremetry, phosphorescence, etc.) can be used if it is necessary to test for cleanup down to a required background level. This test method can also be used for the segregation of soil lots by established contamination levels during on-site construction and excavation.1.1 This test method covers the energy dispersive X-ray fluorescence (EDXRF) spectrochemical analysis of trace levels of uranium and thorium in soils. Any sample matrix that differs from the general ground soil composition used for calibration (that is, fertilizer or a sample of mostly rock) would have to be calibrated separately to determine the effect of the different matrix composition. 1.2 The analysis is performed after an initial drying and grinding of the sample, and the results are reported on a dry basis. The sample preparation technique used incorporates into the sample any rocks and organic material present in the soil. This test method of sample preparation differs from other techniques that involve tumbling and sieving the sample. 1.3 Linear calibration is performed over a concentration range from 20 to 1000 [mu]g per gram for uranium and thorium. 1.4 The values stated in SI units are to be regarded as the standard. The inch-pound units 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Test Method for Analysis of Uranium and Thorium in Soils by Energy Dispersive X-Ray Fluorescence Spectroscopy

ASTM C1075-93(2004) 铀精矿取样标准规程

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 C 967).1.2 These practices also provide for obtaeining 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 C 1022). 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.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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Practices for Sampling Uranium-Ore Concentrate

ASTM D5411-93(1999) 反应堆冷却剂中放射性核素混合物中每次裂变的平均能量的标准计算规程

1.1 This practice applies to the calculation of the average energy per disintegration (E) for a mixture of radionuclides in reactor coolant water. 1.2 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Practice for Calculation of Average Energy Per Disintegration (E) for a Mixture of Radionuclides in Reactor Coolant

ASTM C1075-93(1997) 铀精矿取样的标准规程

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). 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 4 Two-stage falling stream 5 Auger 6 Secondary Sampling Straight-path (reciprocating) 7 Rotating (Vezin) 8, 9 Sample Preparation 10 Concurrent-drying 11 to 13 Natural moisture 14 to 16 Calcination 17, 18 Sample Packaging 19 Wax sealing 20 Vacuum sealing 21 1.3.1 The primary and secondary sampling stages can be organized in the following way: PRIMARY SAMPLING (sections 4 to 6) ------------------------------------

Standard Practices for Sampling Uranium-Ore Concentrate