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Significance and Use
5.1 Plutonium and uranium mixtures are used as nuclear reactor fuels. For use as a nuclear reactor fuel, the material must meet certain criteria for combined uranium and plutonium content, effective fissile content, and impurity content as described in Specifications C757 and C833. After dissolution using one of the procedures described in this practice, the material is assayed for plutonium and uranium to determine if the content is correct as specified by the purchaser.
5.2 Unique plutonium materials, such as alloys, compounds, and scrap metals, are typically dissolved with various acid mixtures or by fusion with various fluxes. Many plutonium salts are soluble in hydrochloric acid. One or more of the procedures included in this practice may be effective for some of these materials; however their applicability to a particular plutonium material shall be verified by the user.
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. Aliquots 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 Procedures in this practice are intended for the dissolution of plutonium metal, plutonium oxide, and uranium-plutonium mixed oxides. Aliquots of dissolved samples are analyzed using test methods, such as those developed by Subcommittee C26.05 on Methods of Test, to demonstrate compliance with applicable requirements. These may include product specifications such as Specifications C757 and C833.
1.3 One or more of the procedures in this practice may be applicable to unique plutonium materials, such as alloys, compounds, and scrap materials. The user must determine the applicability of this practice to such materials.
1.4 The treatments, in order of presentation, are as follows:
Procedure Number | Procedure Title | Section |
1 | Dissolution of Plutonium Metal with Hydrochloric Acid at Room Temperature | 9 |
2 | Dissolution of Plutonium Metal with Hydrochloric Acid and Heating | 10 |
3 | Dissolution of Plutonium Metal with Sulfuric Acid | 11 |
4 | Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed | 12 |
5 | Dissolution of Plutonium Oxide and Uranium-Plutonium Mixed Oxides by Sodium Bisulfate Fusion | 13 |
6 | Dissolution of Uranium-Plutonium Mixed Oxides and Low-Fired Plutonium Oxide in Beakers | 14 |
7 | Open-Vessel (with Reflux Condenser) Dissolution of Plutonium Oxide Powder | 15 |
8 | Open-Vessel (with Reflux Condenser) Dissolution of Mixed Oxide Powder | 16 |
9 | Closed-Vessel Hot Block Dissolution of Plutonium Oxide Powder | 17 |
10 | Open-Vessel (with Reflux Condenser) Dissolution of Mixed Oxide Pellets | 18 |
1.5 The values stated in SI units are to be regarded as standard. Values in parentheses (non-SI units), where provided, are for information only and are not considered standard.
1.6 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
C1145 Terminology of Advanced Ceramics
C1210 Guide for Establishing a Measurement System Quality Control Program for Analytical Chemistry Laboratories Within the Nuclear Industry
D1193 Specification for Reagent Water
D7439 Test Method for Determination of Elements in Airborne Particulate Matter by Inductively Coupled Plasma-Mass Spectrometry
E1154 Specification for Piston or Plunger Operated Volumetric Apparatus
ISO Standards
ISO 8655 Piston-Operated Volumetric Instruments (6 parts)ICS Code
ICS Number Code 27.120.30 (Fissile materials and nuclear fuel technology)
UNSPSC Code
UNSPSC Code 12141735(Plutonium Pu)
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DOI: 10.1520/C1168-15
Citation Format
ASTM C1168-15, Standard Practice for Preparation and Dissolution of Plutonium Materials for Analysis, ASTM International, West Conshohocken, PA, 2015, www.astm.org
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