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

ASTM C1255-93(1999) 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

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 C1219-92(1997) 六氟化铀中砷含量的标准试验方法

1.1 These test methods are applicable to the determination of total arsenic in uranium hexafluoride (UF6) by atomic absorption spectrometry. Two test methods are given: Test Method A-Arsine Generation-Atomic Absorption (Sections 5 to 10), and Test Method B-Graphite Furnace Atomic Absorption (Sections 11 to 16). 1.2 The test methods are equivalent. The limit of detection for each test method is 0.1 [mu]g As/g U when using a sample containing 0.5 to 1.0 g U. 1.3 Test Method A covers the measurement of arsenic in uranyl fluoride (UO2F2) solutions by converting arsenic to arsine and measuring the arsine vapor by flame atomic absorption spectrometry. 1.4 Test Method B utilizes a solvent extraction to remove the uranium from the UO2F2 solution prior to measurement of the arsenic by graphite furnace atomic absorption spectrometry. 1.5 Both insoluble and soluble arsenic are measured when UF6 is prepared according to Test Method C761. 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 Test Methods for Arsenic in Uranium Hexafluoride

ASTM C1221-92(2004) γ射线光谱法无损分析均相溶液中特种核材料的标准试验方法

This test method is a nondestructive means of determining the nuclide concentration of a solution for special nuclear material accountancy, nuclear safety, and process control. It is assumed that the nuclide to be analyzed is in a homogeneous solution (Practice C 1168). The transmission correction makes the test method independent of matrix and useful over several orders of magnitude of nuclide concentrations. However, a typical configuration will normally span only two to three orders of magnitude. The test method assumes that the sample-detector geometry is the same for all measured items. This can be accomplished by requiring that the liquid height in the sidelooking geometry exceeds the detector field of view defined by the collimator. For the uplooking geometry, a fixed sample fill height must be maintained and vials of identical radii must be used unless the vial radius exceeds the field of view defined by the collimator. Since gamma-ray systems can be automated, the test method can be rapid, reliable, and not labor intensive. This test method may be applicable to in-line or off-line situations.1.1 This test method covers the determination of the concentration of gamma-ray emitting special nuclear materials dissolved in homogeneous solutions. The test method corrects for gamma-ray attenuation by the sample and its container by measurement of the transmission of a beam of gamma rays from an external source (Refs. (1), (2), and (3)).1.2 Two sample geometries, slab and cylinder, are considered. The sample container that determines the geometry may be either a removable or a fixed geometry container. This test method is limited to sample containers having walls or a top and bottom of equal transmission through which the gamma rays from the external transmission correction source must pass.1.3 This test method is typically applied to radionuclide concentrations ranging from a few milligrams per litre to several hundred grams per litre. The assay range will be a function of the specific activity of the nuclide of interest, the physical characteristics of the sample container, counting equipment considerations, assay gamma-ray energies, sample matrix, gamma-ray branching ratios, and interferences.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 hazards, see Section 9.

Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry

ASTM C1221-92(1998) γ射线光谱法无损分析均相溶液中特种核材料的标准试验方法

1.1 This test method is applicable to the determination of the concentration of gamma-ray emitting special nuclear materials dissolved in homogeneous solutions. The test method corrects for gamma-ray attenuation by the sample and its container by measurement of the transmission of a beam of gamma rays from an external source (Refs. (1), (2), and (3)). 1.2 Two sample geometries, slab and cylinder, are considered. The sample container that determines the geometry may be either a removable or a fixed geometry container. This test method is limited to sample containers having walls or a top and bottom of equal transmission through which the gamma rays from the external transmission correction source must pass. 1.3 This test method is typically applied to radionuclide concentrations ranging from a few mg/L to several hundred g/L. The assay range will be a function of the specific activity of the nuclide of interest, the physical characteristics of the sample container, counting equipment considerations, assay gamma-ray energies, sample matrix, gamma-ray branching ratios, and interferences. 1.4 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. For specific hazards, see Section 8.

Standard Test Method for Nondestructive Analysis of Special Nuclear Materials in Homogeneous Solutions by Gamma-Ray Spectrometry

ASTM C1204-91(1996) 在有钚存在的情况下经铬(VI)滴定后用磷酸中铁(II)量减少法测定铀的试验方法

1.1 This test method covers unirradiated uranium-plutonium mixed oxide having a uranium to plutonium ratio of 2.5 and greater. The presence of larger amounts of plutonium (Pu) that give lower uranium to plutonium ratios may give low analysis results for uranium (U) (1), if the amount of plutonium together with the uranium is sufficient to slow the reduction step and prevent complete reduction of the uranium in the allotted time. Use of this test method for lower uranium to plutonium ratios may be possible, especially when 20 to 50 mg quantities of uranium are being titrated rather than the 100 to 300 mg in the study cited in Ref (1). Confirmation of that information should be obtained before this test method is used for ratios of uranium to plutonium less than 2.5.1.2 The amount of uranium determined in the data presented in Section was 20 to 50 mg. However, this test method, as stated, contains iron in excess of that needed to reduce the combined quantities of uranium and plutonium in a solution containing 300 mg of uranium with uranium to plutonium ratios greater than or equal to 2.5. Solutions containing up to 300 mg uranium with uranium to plutonium ratios greater than or equal to 2.5 have been analyzed (1) using the reagent volumes and conditions as described in Section 10.1.3 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. For specific hazard statements, see Section 8.

Standard Test Method for Uranium in the Presence of Plutonium by Iron(II) Reduction in Phosphoric Acid Followed by Chromium(VI) Titration

ASTM C1206-91(1996) 铁(II)/铬(VI)安培计滴定法测定钚的试验方法

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 C757-90(2002) 核纯级可烧结的二氧化钚粉末的规格

1.1 This specification covers nuclear grade plutonium dioxide, sinterable powder obtained by the oxalate precipitation route, calcined above 500176;C, or any other equivalent process acceptable to the purchaser. Included is plutonium dioxide of various isotopic compositions as normally prepared by in-reactor neutron irradiation of natural- or slightly enriched uranium or by in-reactor neutron irradiation of recycled plutonium mixed with uranium.1.2 There is no discussion of or provision for preventing criticality incidents, nor are health and safety requirements, the avoidance of hazards, or shipping precautions and controls discussed. Observance of this specification does not relieve the user of the obligation to be aware of and conform to all Federal, state, and local regulations on processing, shipping, or using source or special nuclear materials. Examples of U.S. Government documents are N7.2 Radiation Protection in Nuclear Reactor Fuel Fabrication Plants, Code of Federal Regulations, Title 10 Nuclear Safety Guide, U.S. Atomic Energy Commission Report TID-7016, and "Handbook of Nuclear Safety", H. K. Clark, U.S. Atomic Energy Commission Report, DP-532.1.3 The PuO2 shall be produced by the processor employing a qualified process and in accordance with a quality assurance program approved by the user.1.4 The values stated in SI units are to be regarded as 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable

ASTM C1168-90(1995)e1 分析用钚材料的制备和溶解的标准实施规程

1.1 This practice is a compilation of dissolution techniques for plutonium materials that are applicable to the test methods used for characterizing these materials. Dissolution treatments for the major plutonium materials assayed for plutonium or analyzed for other components are listed. Aliquants of the dissolved samples are dispensed on a weight basis when one of the analyses must be highly reliable, such as plutonium assay; otherwise they are dispensed on a volume basis.1.2 The treatments, in order of presentation, are as follows:Procedure TitleSectionDissolution of Plutonium Metal with Hydrochloric Acid7.1Dissolution of Plutonium Metal with Sulfuric Acid7.2Dissolution of Plutonium Oxide and Uranium-Plutonium MixedOxide by the Sealed-Reflux Technique7.3Dissolution of Plutonium Oxide and Uranium-Plutonium MixedOxides by Sodium Bisulfate Fusion7.4Dissolution of Uranium-Plutonium Mixed Oxides and Low-FiredPlutonium Oxide in Beakers7.51.3 The values stated in SI units are to be regarded as 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 Practice for Preparation and Dissolution of Plutonium Materials for Analysis

ASTM E385-90(2002) 使用14兆电子伏特的中子活化和直接计数技术测定含氧量的试验方法

1.1 This test method covers the measurement of oxygen concentration in almost any matrix by using a 14-MeV neutron activation and direct-counting technique. Essentially, the same system may be used to determine oxygen concentrations ranging from over 50 % to about 10 956;g/g, or less, depending on the sample size and available 14-MeV neutron fluence rates. Note 18212;The range of analysis may be extended by using higher neutron fluence rates, larger samples, and higher counting efficiency detectors.1.2 This test method may be used on either solid or liquid samples, provided that they can be made to conform in size, shape, and macroscopic density during irradiation and counting to a standard sample of known oxygen content. Several variants of this method have been described in the technical literature. A monograph is available which provides a comprehensive description of the principles of activation analysis using a neutron generator (1).1.3 The values stated in either SI or inch-pound units are to be regarded separately 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 precautions are given in Section 8.

Standard Test Method for Oxygen Content Using a 14-MeV Neutron Activation and Direct-Counting Technique

ASTM C1165-90(2005) 用控制电位库仑计法在铂工作电极上测定硫酸中钚的标准试验方法

This test method is to be used to ascertain whether or not materials meet specifications for plutonium content or plutonium assay, or both. A chemical calibration of the coulometer is necessary for accurate results. FIG. 1 Example of a Cell Design Used at Los Alamos National Laboratory (LANL)1.1 This test method covers the determination of milligram quantities of plutonium in unirradiated uranium-plutonium mixed oxide having a U/Pu ratio range of 0.1 to 10. This test method is also applicable to plutonium metal, plutonium oxide, uranium-plutonium mixed carbide, various plutonium compounds including fluoride and chloride salts, and plutonium solutions.1.2 The recommended amount of plutonium for each aliquant in the coulometric analysis is 5 to 10 mg. Precision worsens for lower amounts of plutonium, and elapsed time of electrolysis becomes impractical for higher amounts of plutonium.1.3 The values stated in SI units are to be regarded as standard. No other units are to be regarded as standard.1.4 This standard does not purport to address all of the safety concens, 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 Section 8.

Standard Test Method for Determining Plutonium by Controlled-Potential Coulometry in H₂SO₄ at a Platinum Working Electrode

ASTM C1165-90(2000)e1 用控制电位库仑计法在铂工作电极上测定硫酸中钚的标准试验方法

1.1 This test method describes the determination of milligram quantities of plutonium in unirradiated uranium-plutonium mixed oxide having a U/Pu ratio range of 0.1 to 10. This test method is also applicable to plutonium metal, plutonium oxide, uranium-plutonium mixed carbide, various plutonium compounds including fluoride and chloride salts, and plutonium solutions. 1.2 The recommended amount of plutonium for each aliquant in the coulometric analysis is 5 to 10 mg. Precision worsens for lower amounts of plutonium, and elapsed time of electrolysis becomes impractical for higher amounts of plutonium. 1.3 The values stated in SI units are to be regarded as 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. Specific precautionary statements are given in Section 8.

Standard Test Method for Determining Plutonium by Controlled-Potential Coulometry in H₂SO₄ at a Platinum Working Electrode

ASTM C1110-88(1997)e1 使用玻璃熔化或压制粉末法制备矿石中铀的X射线发射光谱分析用样品的标准规程

1.1 This practice covers the preparation of uranium ore samples to be analyzed by X-ray emission. Two separate techniques, the glass fusion method or the pressed powder method, may be used. 1.2 The values stated in SI (metric) units are to be regarded as the 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 and health practices and determine the applicability of regulatory limitations prior to use.

Standard Practice for Sample Preparation for X-Ray Emission Spectrometric Analysis of Uranium in Ores Using the Glass Fusion or Pressed Powder Method

ASTM C982-88(1997)e1 能量扩散的X射线荧光系统的构件选择标准指南

1.1 This guide describes the components for an energy-dispersive X-ray fluorescence (XRF) system for materials analysis. It can be used as a reference in the apparatus section of test methods for energy-dispersive X-ray fluorescence analyses of nuclear materials. 1.2 The components recommended include X-ray detectors, signal processing electronics, data acquisition and analysis systems, and excitation sources that emit photons (See Fig. 1). 1.3 Detailed data analysis methods are not described or recommended, as they may be unique to a particular analysis problem. Some applications may require the use of spectrum deconvolution to separate partially resolved peaks or to correct for matrix effects in data reduction. 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 Selecting Components for Energy-Dispersive X-Ray Fluorescence (XRF) Systems

ASTM C970-87(1997) 多个容器堆中专用核材料取样

1.1 This practice provides an aid in designing a sampling and analysis plan for the purpose of minimizing random error in the measurement of the amount of nuclear material in a lot consisting of several containers. The problem addressed is the selection of the number of containers to be sampled, the number of samples to be taken from each sampled container, and the number of aliquot analyses to be performed on each sample. 1.2 This practice provides examples for application as well as the necessary development for understanding the statistics involved. The uniqueness of most situations does not allow presentation of step-by-step procedures for designing sampling plans. It is recommended that a statistician experienced in materials sampling be consulted when developing such plans. 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.

Standard Practice for Sampling Special Nuclear Materials in Multi-Container Lots

ASTM C791-83(2000) 核纯级碳化硼的化学分析,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 boron carbide powder and pellets to determine compliance with specifications.1.2 The analytical procedures appear in the following order: SectionsTotal Carbon by Combustion and Gravimetry7-17Total Boron by Titrimetry18-28Isotopic Composition by Mass Spectrometry29-38Chloride and Fluoride Separation by Pyrohydrolysis39-45Chloride by Constant-Current Coulometry46-54Fluoride by Ion-Selective Electrode55-63Water by Constant-Voltage Coulometry64-72Impurities by Spectrochemical Analysis73-81Soluble Boron by Titrimetry82-95Soluble Carbon by a Manometric Measurement96-105Metallic Impurities by a Direct Reader Spectrometric Method106-1141.3 This method covers the determination of total carbon in nuclear-grade, boron carbide in either powder or pellet form.1.4 This method covers the determination of total boron in samples of boron carbide powder and pellets. The recommended amount of boron for each titration is 100 10 mg.1.5 This method covers the determination of the isotopic composition of boron in nuclear-grade boron carbide, in powder and pellet form, containing natural to highly enriched boron.1.6 This method covers the separation of up to 100 g of halides per gram of boron carbide. The separated halides are measured using other methods found in this standard.1.7 This method covers the measurement of chloride after separation from boron carbide by pyrohydrolysis. The lower limit of the method is about 2 g of chloride per titration.1.8 This method covers the measurement of fluoride after separation from boron carbide by pyrohydrolysis. The lower limit of the method is about 2 g of fluoride per measurement.1.9 This method covers the determination of water in boron carbide in either powder or pellet form. The lower limit of the method is 5 g of water.1.10 This method covers the determination of 14 impurity elements in boron carbide in either powder or pellet form.1.11 This method covers the determination of soluble boron in boron carbide. Soluble boron is defined as that boron dissolved under the conditions of the test.1.12 This method covers the determination of soluble carbon in boron carbide. The lower limit of the method is 0.02 % with a 100-mg sample. Soluble carbon is defined as that carbon oxidized by the sodium dichromate-sulfuric acid solution under the conditions of this method.1.13 This method is applicable to the determination of metallic impurities in samples of boron carbide powder and pellets. From 20 to 5000 g of many of the impurities per gram of sample can be determined.

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