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Perchloric acid dissolution of graphite and pyrolytic carbon
1General Atomic Company, P.O. Box 81608, San Diego, California 92138, U.S.A.
Talanta
|June 1, 1977
Summary
Three wet oxidation procedures using perchloric acid effectively dissolve nuclear graphite, pyrocarbon-coated fuel, and carbonaceous materials. These methods are crucial for analyzing both irradiated and unirradiated high-temperature gas-cooled reactor components.
Area of Science:
- Nuclear Engineering
- Materials Science
- Analytical Chemistry
Background:
- High-temperature gas-cooled reactors (HTGRs) utilize specialized carbonaceous materials like nuclear graphite and pyrocarbon-coated fuel particles.
- Accurate analysis of these materials, especially after irradiation, is essential for safety and performance evaluation.
- Existing dissolution methods may not be suitable for all HTGR carbonaceous components or for both irradiated and unirradiated samples.
Purpose of the Study:
- To develop and describe three distinct wet oxidation procedures for dissolving various carbonaceous materials found in HTGRs.
- To enable the analysis of irradiated and unirradiated nuclear graphite, pyrocarbon-coated fuel particles, and other carbonaceous materials.
- To facilitate pre-analysis dissolution for fission-product and burn-up studies.
Main Methods:
- Wet oxidation using perchloric acid as the primary oxidizing agent.
- Procedure 1: Dissolution of bulk nuclear graphite and pyrolytic carbon.
- Procedure 2: Dissolution of milligram quantities of HTGR fuel particles.
- Procedure 3: Dissolution of more easily oxidized materials like charcoal.
Main Results:
- Successful development of three distinct wet oxidation procedures tailored to different carbonaceous materials.
- Demonstrated efficacy of perchloric acid in dissolving nuclear graphite, pyrocarbon coatings, and charcoal.
- Applicability of the procedures for both irradiated and unirradiated materials.
Conclusions:
- The described wet oxidation procedures provide reliable methods for dissolving diverse HTGR carbonaceous materials.
- These methods are valuable for pre-analysis dissolution, particularly for irradiated fuel and graphite components.
- The procedures support essential fission-product and burn-up analyses in HTGR research and development.
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