ASTM C1347-08(2023) PDF
Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis
Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis
- Статус документа:
- Действующий
- Формат:
- Электронный (PDF)
- Количество страниц:
- 9
- Дата публикации:
- 1 января 2023 г.
- Издание:
- C1347
- ICS:
- 27.120.30
SIGNIFICANCE AND USE 4.1 The materials covered that must meet ASTM specifications are uranium metal and uranium oxide. 4.2 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 C753 and C776. The material is assayed for uranium to determine whether the content is as specified. 4.3 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. SCOPE 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 Title Section Dissolution of Uranium Metal and Oxide with Nitric Acid 8.1 Dissolution of Uranium Oxides with Nitric Acid and Residue Treatment 8.2 Dissolution of Uranium-Aluminum Alloys in Hydrochloric Acid with Residue Treatment 8.3 Dissolution of Uranium Scrap and Ash by Leaching with Nitric Acid and Treatment of Residue by Carbonate Fusion 8.4 Dissolution of Refractory Uranium-Containing Material by Carbonate Fusion 8.5 Dissolution of Uranium—Aluminum Alloys Uranium Scrap and Ash, and Refractory Uranium-Containing Materials by Microwave Treatment 8.6 1.3 The values stated in SI units are to be regarded as standard. No other units of measurement are included in this 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. Specific hazards statements are 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.
Abstract
Overview
ASTM C1347-08(2023) - Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis provides the key procedures for the preparation and dissolution of uranium-bearing materials prior to chemical analysis. This standard, maintained by ASTM International, ensures accurate quantification of uranium content, isotopic composition, and impurities - essential for nuclear fuel quality, safety, and regulatory compliance.
The practice applies to uranium metal, uranium oxide, and related materials, outlining specific dissolution techniques for reliable laboratory characterization. These procedures are crucial for meeting the stringent criteria for nuclear reactor fuel as described in other relevant ASTM specifications.
Key Topics
-
Dissolution Techniques: The standard covers a range of methods using various acids and fusion processes to dissolve uranium metal, uranium oxides, uranium-aluminum alloys, scrap, ash, and refractory uranium-containing materials. Specific approaches include:
- Dissolution with nitric acid (for metals and oxides)
- Hydrochloric acid treatments (especially for uranium-aluminum alloys)
- Microwave-assisted dissolution for challenging matrices
- Fusion with sodium carbonate or bisulfate for residues
-
Sample Handling and Preparation: Guidelines for quantitative transfer of material, prevention of cross-contamination, and steps to ensure complete or near-complete dissolution are provided to support high-precision analytical work.
-
Apparatus and Reagents: Details on required labware (glassware, plasticware, platinum crucibles), balances, furnaces, and reagent purity are specified to support accurate analysis and trace impurity measurement.
-
Safety Practices: Emphasis on safe handling of radioactive, toxic, and corrosive materials, including uranium compounds and acids such as hydrofluoric acid. The standard highlights the need for appropriate laboratory facilities and adherence to safety protocols.
Applications
ASTM C1347-08(2023) is integral to:
- Nuclear Fuel Manufacturing: Ensuring the uranium input meets the strict material and impurity specification for nuclear-reactor fuel elements.
- Quality Control & Assurance: Supporting routine and investigative analyses of uranium materials to monitor consistency and compliance.
- Research & Development: Offering standardized practices for dissolving uranium samples in R&D labs, including the processing of uranium-containing residues, alloys, and unique forms.
- Regulatory Compliance: Providing a recognized method that helps organizations satisfy national and international nuclear material handling standards.
- Waste Management: Facilitating the analysis of uranium-containing scrap and ash for waste minimization or recovery operations.
Related Standards
Organizations working with uranium materials often reference additional ASTM standards for comprehensive quality management and analysis:
- ASTM C753 - Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
- ASTM C776 - Specification for Sintered Uranium Dioxide Pellets for Light Water Reactors
- ASTM C1168 - Practice for Preparation and Dissolution of Plutonium Materials for Analysis
- ASTM D1193 - Specification for Reagent Water
These standards, when used in conjunction with ASTM C1347-08(2023), help ensure complete adherence to best practices in uranium analysis and nuclear fuel production.
Keywords: uranium dissolution, uranium analysis, sample preparation, nuclear fuel, uranium oxide, uranium metal, uranium alloys, ASTM C1347-08(2023), uranium impurities, uranium assay, nuclear industry standards, laboratory safety, reagent purity, trace analysis.
Технические детали
- Технический комитет
- C26 - Nuclear Fuel Cycle
- SKU
- ASTM C1347-08(2023)
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