ASTM C1168-01
Historical Standard: ASTM C1168-01 Standard Practice for Preparation and Dissolution of Plutonium Materials for Analysis
SUPERSEDED (see Active link, below)
ASTM C1168
1. Scope
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 Title | Section |
| Dissolution of Plutonium Metal with Hydrochloric Acid | 7.1 |
| Dissolution of Plutonium Metal with Sulfuric Acid | 7.2 |
| Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxide by the Sealed-Reflux Technique | 7.3 |
| Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxides by Sodium Bisulfate Fusion | 7.4 |
| Dissolution of Uranium-Plutonium Mixed Oxides and Low-Fired Plutonium Oxide in Beakers | 7.5 |
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.
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
C757 Specification for Nuclear-Grade Plutonium Dioxide Powder, Sinterable
C833 Specification for Sintered (Uranium-Plutonium) Dioxide Pellets
C859 Terminology Relating to Nuclear Materials
C1008 Specification for Sintered (Uranium-Plutonium) Dioxide Pellets--Fast Reactor Fuel
Keywords
compilation of dissolution techniques; plutonium analysis preparation; plutonium dissolution; plutonium metal dissolution; plutonium oxide dissolution; uranium-plutonium mixed oxide dissolution; Chemical analysis--nuclear materials; Contamination--nuclear; Dissolution; Plutonium; Plutonium solutions; Specimen preparation (for testing)--nuclear applications; Uranium-plutonium mixed oxide;
ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
DOI: 10.1520/C1168-01
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