title: Perchloric acid dissolution of graphite and pyrolytic carbon.
abstract: Three procedures are described for the wet oxidation, with perchloric acid, of nuclear graphite, pyrocarbon-coated fuel particles, and other carbonaceous materials used in high-temperature gas-cooled nuclear reactors (HTGRs). The first procedure is for dissolution of graphite and pyrolytic carbon, the second for dissolution of milligram quantities of HTGR fuel particles, and the last for dissolution of more easily oxidized carbonaceous materials such as charcoal. These procedures were developed primarily for the dissolution of irradiated materials before fission-product or burn-up analyses, but they are also used for dissolution of unirradiated materials.
authors.affiliation: General Atomic Company, P.O. Box 81608, San Diego, California 92138, U.S.A.
authors.forename: G
authors.initials: G
authors.lastname: Buzzelli
authors.forename: A W
authors.initials: AW
authors.lastname: Mosen