Dissolution of Irradiated Commercial UO2 Fuels in Ammonium Carbonate and Hydrogen Peroxide

Autor:	Shane M. Peper, Amanda M. Johnsen, Katharine J. Carson, Bruce K. McNamara, Brady D. Hanson, Jeffrey W. Chenault, Chuck Z. Soderquist
Rok vydání:	2011
Předmět:	Ammonium carbonate Fission products Nuclear fuel Curium General Chemical Engineering Radiochemistry Inorganic chemistry chemistry.chemical_element Americium General Chemistry PUREX Industrial and Manufacturing Engineering chemistry.chemical_compound chemistry Carbonate Dissolution
Zdroj:	Industrial & Engineering Chemistry Research. 50:1813-1818
ISSN:	1520-5045 0888-5885
DOI:	10.1021/ie101386n
Popis:	We propose and test a disposition path for irradiated nuclear fuel using ammonium carbonate and hydrogen peroxide media. We demonstrate on a 13 g scale that >98% of the irradiated fuel dissolves. Subsequent expulsion of carbonate from the dissolver solution precipitates >95% of the plutonium, americium, and curium and substantial amounts of fission products, effectively partitioning the fuel at the dissolution step. Uranium can be easily recovered from solution by any of several means, such as ion exchange, solvent extraction, or direct precipitation. Ammonium carbonate can be evaporated from solution and recovered for reuse, leaving an extremely compact volume of fission products, transactinides, and uranium. Stack emissions are predicted to be less toxic, less radioactive, chemically simpler, and simpler to treat than those from the conventional PUREX process.
Databáze:	OpenAIRE
Externí odkaz:	https://explore.openaire.eu/search/publication?articleId=doi_________::1eaeeb98f7d00669b8d8476f00be256b https://doi.org/10.1021/ie101386n Zobrazit plný text záznamu