F40 核材料、核燃料综合 标准查询与下载

EJ/T 1162-2002 地浸砂岩型铀矿地球物理测井规范

本标准规定了地浸砂岩型铀矿地球物理测井的设计、仪器设备、施工准备、测量技术、原始资料质 量評價、资料处理与解释、报告编写及安全防护等方面的技术要求。 本标准适用于地浸砂岩型铀矿地球物理测井工作。煤田、水文、工程及环境地质勘查中的测井工作 可参照使用。

Specifications of geophysical logging on in-situ leaching sandstone type uranium deposits

EJ/T 1161-2002 1:500000地浸砂岩型铀资源区域评价规范

Specifications of 1:500000 regional evaluation on in-situ leaching sandstone type uranium resources

EJ/T 1160-2002 1:250000地浸砂岩型铀资源区域评价规范

本标准规定了中新生代沉积盆地1 : 250000地浸砂岩型铀资源区域评价的目的、任务、基本准则、 工作程序、工作方法、工作内容、工作程度和报告编写的基本内容及有关技术要求。 本标准适用于1 : 250000地漫砂岩型铀资源区域评价的工作部署、设计编号、野外实施，可作为 质量监控和验收、评审地浸砂岩型铀资源区域评价报告的依据。

Specifications of 1:250000 regional evaluation on in-situ leaching sandstone type uranium resources

EJ/T 1159-2002 地浸砂岩型铀矿钻探工程地质物探原始编录规范

本标准规定了地漫砂岩型铀矿钻探工程中地质物探原始编录的目的任务、技术要求、工作程序、编 錄內容、资料整理及检查验收等。 本标准适用于地漫砂岩型铀矿钻探工程地质物探岩(矿) 心编录。

Specifications of initial geological-geophysical documentation on in-situ leaching sandstone type uranium deposits

EJ/T 1158-2002 地浸砂岩型铀矿取样规范

Specifications of sampling for in-situ leaching sandstone type uranium deposits

EJ/T 1154-2002 后处理三氧化铀粉末技术条件

Specification for reprocessed uranium trioxide

EJ/T 1147-2002 核级二氧化钚粉末技术条件

Specification for nuclear - grade plutonium dioxide powder

EJ/T 1140-2002 地浸砂岩型铀矿钻探规范

Drilling specifications on in-situ leaching sandstone uranium deposit

ASTM C1347-02 分析用铀材料制备和溶解的标准实施规程

The materials covered that must meet ASTM specifications are uranium metal and uranium oxide. Uranium materials are used as nuclear reactor fuel. For this use, these materials must meet certain criteria for uranium content, uranium-235 enrichment, and impurity content, as described in Specifications C 753 and C 776. The material is assayed for uranium to determine whether the content is as specified. Uranium alloys, refractory uranium materials, and uranium containing scrap and ash are unique uranium materials for which the user must determine the applicability of this practice. In general, these unique uranium materials are dissolved with various acid mixtures or by fusion with various fluxes.1.1 This practice covers dissolution treatments for uranium materials that are applicable to the test methods used for characterizing these materials for uranium elemental, isotopic, and impurities determinations. Dissolution treatments for the major uranium materials assayed for uranium or analyzed for other components are listed.1.2 The treatments, in order of presentation, are as follows:Procedure TitleSectionDissolution of Uranium Metal and Oxide with Nitric Acid8.1Dissolution of Uranium Oxides with Nitric Acid and Residue Treatment8.2Dissolution of Uranium-Aluminum Alloys in Hydrochloric Acid with Residue Treatment8.3Dissolution of Uranium Scrap and Ash by Leaching with Nitric Acid and Treatment of Residue by Carbonate Fusion8.4Dissolution of Refractory Uranium-Containing Material by Carbonate Fusion8.5Dissolution of Uranium-Aluminum Alloys Uranium Scrap and Ash, and RefractoryUranium-Containing Materials by Microwave Treatment8.61.3 The values stated in SI units are to be regarded as the 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 and health practices and determine the applicability of regulatory limitations prior to use. Specific hazards statements are given in Section 7.

Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis

ASTM C1517-02 用直流电弧发射光谱分析法测定铀金属或化合物中金属杂质的标准试验方法

This test method is applicable to uranium metal, uranium oxides and compounds soluble in nitric or sulfuric acid, and uranium solutions which can be converted to uranium oxide (U3O8) in a muffle furnace. It may be used to determine the impurities in uranium compounds as listed in Specifications C 753, C 776, C 788, and C 967.1.1 This test method describes the steps necessary for the preparation and determination of impurity metals in uranium metal and uranium compounds by DC arc emission spectroscopy.1.2 The method is valid for those materials that can be dissolved in acid and/or converted to an oxide in a muffle furnace (see Practice C 1347).1.3 This method uses the carrier distillation technique to selectively carry the impurities into the arc, leaving the uranium oxide in the electrode. If it is necessary to determine the carrier metal(usually a silver or strontium, or gallium compound) as an impurity, another technique must be chosen for that element.1.4 This standard may involve hazardous materials, operations and equipment. 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 Metallic Impurities in Uranium Metal or Compounds by DC-Arc Emission Spectroscopy

ASTM C1514-02 用浓度计原理测量235U分馏物的标准试验方法

The enrichment meter principle provides a nondestructive measurement of the 235U fraction of uranium-bearing items. Sampling is not required and no waste is generated, minimizing exposure to hazardous materials and resulting in reduced sampling error. Use of a low resolution detector (e.g., NaI detector) to measure uranium with 235U fraction approximately 10 % which is contained in a thin-walled container can provide a rapid (typically 100 s), easily portable measurement system with precision of 0.6 % and bias of less than 1 %. Use of a high resolution detector (e.g., high-purity germanium) can provide measurement with a precision better than 0.2 % and a bias less than 1 % within a 300-sec measurement time when measuring uranium with 235U fraction in the range of 0.711 % to 4.46 % which is contained in thin-walled containers. In order to obtain optimum results using this method, the chemical composition of the item must be well known, the container wall must permit transmission of the 185.7 keV gamma ray, and the uranium-bearing material within the item must be infinitely thick with respect to the 185.7 keV gamma ray. Items must be homogeneous with respect to both 235U fraction and chemical composition. The uranium-bearing materials in the measured items and calibration reference materials used for calibration must fill the detector field of view. When measuring items, using low-resolution detectors, in thin-walled containers that have not reached secular equilibrium, either the method should not be used, additional corrections should be made to account for the age of the uranium, or high-resolution measurements should be performed. The method is typically used as a verification technique, not to establish enrichment.1.1 This test method covers the quantitative determination of the fraction of 235U in uranium using measurement of the 185.7 keV gamma ray produced during the decay of 235U.1.2 This test method is applicable to items containing homogeneous uranium-bearing materials of known chemical composition in which the compound is considered infinitely thick with respect to 185.7 keV gamma rays.1.3 This test method can be used for the entire range of 235U fraction, from depleted (0.2 % 235U) to very highly enriched (97.5 % 235U).1.4 Measurement of items that have not reached secular equilibrium between 238U and 234Th, may not produce the stated bias when low-resolution detectors are used with the computational method listed in Appendix B.1.5 This standard may involve hazardous materials, operations, and equipment. 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 Measurement of ²³⁵U Fraction using the Enrichment Meter Principle

ASTM C1022-02 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 C1500-02 用无源中子重复计数法对钚进行无损分析的标准试验方法

1.1 This test method describes the nondestructive assay of plutonium in forms such as metal, oxide, scrap, residue, or waste using passive neutron multiplicity counting. This test method provides rapid results that are usually more accurate than conventional neutron coincidence counting. The method can be applied to a large variety of plutonium items in various geometries in cans, 208-L drums, or 1900-L Standard Waste Boxes. It has been used to assay items whose plutonium content ranges from 1 g to 1000's of g.1.2 There are several electronics or mathematical approaches available for multiplicity analysis, including the shift register, the Euratom Time Correlation Analyzer, and the List Mode Module, as described briefly in Ref. (1).1.3 This test method is primarily intended to address the assay of 240Pu-effective by moments-based multiplicity analysis using shift register electronics (1,2 ) and high efficiency neutron counters specifically designed for multiplicity analysis. This test method requires knowledge of the relative abundances of the plutonium isotopes to determine the total plutonium mass.1.4 This test method may also be applied to modified neutron coincidence counters which were not specifically designed as multiplicity counters, with a corresponding degradation of results.

Standard Test Method for Nondestructive Assay of Plutonium by Passive Neutron Multiplicity Counting

ASTM C967-02a 铀矿浓缩物的标准规范

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 standard 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 the standard. The values given in parentheses are for information only.

Standard Specification for Uranium Ore Concentrate

ASTM C1206-02 铁(II)/铬(VI)安培计滴定法测定钚的试验方法

All plutonium materials covered in this test method are used in the preparation of nuclear-reactor fuels. In order to be suitable for this purpose, the materials must meet specified criteria for plutonium content. This test method is used to verify the plutonium content. A primary standard dichromate such as that available from National Institute of Standards and Technology (NIST) or a dichromate traceable to a primary standard such as New Brunswick Laboratory (NBL) plutonium standard, is required for this technique.1.1 This test method covers the determination of plutonium in unirradiated nuclear-grade plutonium dioxide, uranium-plutonium mixed oxides with uranium (U)/plutonium (Pu) ratios up to 21, plutonium metal, and plutonium nitrate solutions. Optimum quantities of plutonium to measure are 7 to 15 mg.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 by Iron (II)/Chromium (VI) Amperometric Titration

ASTM C1307-02 用(III)钚数组分光光度法鉴定钚的标准测试方法

This test method is designed to determine whether a given material meets the purchaserrsquo;specification for plutonium content.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 C1285-02 确定核废物和混合废弃玻璃及多相玻璃陶瓷耐化学性能的标准试验方法:产品一致性试验(PCT)

These test methods provide data useful for evaluating the chemical durability (see 3.1.4) of glass waste forms as measured by elemental release. Accordingly, it may be applicable throughout manufacturing, research, and development. 5.1.1 Test Method A can specifically be used to obtain data to evaluate whether the chemical durability of glass waste forms have been consistently controlled during production (see Table 1). 5.1.2 Test Method B can specifically be used to measure the chemical durability of glass waste forms under various leaching conditions, for example, varying test durations, test temperatures, ratio of sample-surface area (S) to leachant volume (V) (see Appendix X1), and leachant types (see Table 1). Data from this test may form part of the larger body of data that are necessary in the logical approach to long-term prediction of waste form behavior (see Practice C 1174).1.1 These product consistency test methods A and B evaluate the chemical durability of homogeneous glasses, phase separated glasses, devitrified glasses, glass ceramics, and/or multiphase glass ceramic waste forms hereafter collectively referred to as "glass waste forms" by measuring the concentrations of the chemical species released to a test solution.1.1.1 Test Method A is a seven-day chemical durability test performed at 90 177; 2176;C in a leachant of ASTM-Type I water. The test method is static and conducted in stainless steel vessels. Test Method A can specifically be used to evaluate whether the chemical durability and elemental release characteristics of nuclear, hazardous, and mixed glass waste forms have been consistently controlled during production. This test method is applicable to radioactive and simulated glass waste forms as defined above.1.1.2 Test Method B is a durability test that allows testing at various test durations, test temperatures, mesh size, mass of sample, leachant volume, and leachant compositions. This test method is static and can be conducted in stainless steel or PFA TFE-fluorocarbon vessels, or both. Test Method B can specifically be used to evaluate the relative chemical durability characteristics of homogeneous glasses, phase separated glasses, devitrified glasses, glass ceramics, and/or multiphase glass ceramic waste forms. This test method is applicable to radioactive (nuclear) and mixed, hazardous, and simulated waste forms as defined above. Test Method B cannot be used as a consistency test for production of high level radioactive glass waste forms.1.2 These test methods must be performed in accordance with all quality assurance requirements for acceptance of the data.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 Methods for Determining Chemical Durability of Nuclear, Hazardous, and Mixed Waste Glasses and Multiphase Glass Ceramics: The Product Consistency Test (PCT)

ASTM C1539-02 用液体闪烁计数法测定六氟化铀中锝-99的标准试验方法

Uranium hexafluoride is a basic material used to prepare nuclear reactor fuel. To be suitable for this purpose, the material must meet the criteria for technetium composition. This test method is designed to determine whether the material meets the requirements described in Specifications C 787 and C 996. Using the specified instrumentation and parameters, this method has a lower detection limit of 0.0004μgTc/gU. Note 18212;Different instrumentation or parameters may provide varying detection limits, as calculated in 11.4.1.1 This test method is a quantitative method used to determine technetium-99 (99Tc) in uranium hexafluoride (UF 6) by liquid scintillation counting.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 Determination of Technetium-99 in Uranium Hexafluoride by Liquid Scintillation Counting

EJ/T 629-2001 压水堆燃料组件机械设计和评价

本标准规定了压水堆燃料組件(簡稱 “燃料組件” ) 機械設計和評價應滿足的要求。 本标准适用于燃料组件机械设计和评价。

Presurized water reactors fuel assembly mechanical design and evaluation

NF M60-402*NF ISO 8298:2001 核燃料技术.硝酸溶液中钚的毫克量的测定.经铈氧化和铁还原后用重铬酸钾的电位滴定法

Nuclear fuel technology - Determination of milligram amounts of plutonium in nitric acid solutions - Potentiometric titration with potassium dichromate after oxidation by Ce(IV) and reduction by Fe(II).