ASTM C1347 - 08(2014)e1
Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis
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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.
1. 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 | 8.2 |
| Dissolution of Uranium-Aluminum Alloys in Hydrochloric Acid | 8.3 |
| Dissolution of Uranium Scrap and Ash by Leaching with Nitric | 8.4 |
| Dissolution of Refractory Uranium-Containing Material by | 8.5 |
| Dissolution of Uranium—Aluminum Alloys | 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 and health practices and determine the applicability of regulatory limitations prior to use. Specific hazards statements are given in Section 7.
2. Referenced Documents (purchase separately) The documents listed below are referenced within the subject standard but are not provided as part of the standard.
ASTM Standards
C753 Specification for Nuclear-Grade, Sinterable Uranium Dioxide Powder
C776 Specification for Sintered Uranium Dioxide Pellets
C1168 Practice for Preparation and Dissolution of Plutonium Materials for Analysis
D1193 Specification for Reagent Water
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
UNSPSC Code
UNSPSC Code 15131500(Nuclear fuel); 12141748(Uranium U)
Referencing This Standard
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DOI: 10.1520/C1347-08R14E01
Citation Format
ASTM C1347-08(2014)e1, Standard Practice for Preparation and Dissolution of Uranium Materials for Analysis, ASTM International, West Conshohocken, PA, 2014, www.astm.org
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