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Studies on disintegrating spherical fuel elements of high temperature gas-cooled reactor by a electrochemical method
Authors:Lifang Tian  Mingfen Wen  Jing Chen
Affiliation:1. Dipartimento di Energia, Politecnico di Milano, Milan, Italy;2. Istituto di Fisica del Plasma, Consiglio Nazionale delle Ricerche, EURATOM-ENEA-CNR Association, Milan, Italy;3. Center for Nano Science and Technology @ Polimi, Istituto Italiano di Tecnologia, Milan, Italy;4. Dipartimento di Meccanica, Politecnico di Milano, Milan, Italy;1. Department of Physics, University of Science and Technology Beijing, Beijing 100083, PR China;2. Nuclear Engineering Program, The Ohio State University, Columbus, OH 43210, USA;3. Accelarator Laboratories, School of Physics, Wuhan University, Wuhan, Hubei 430072, PR China;4. Key Laboratory of Nuclear Analysis Techniques, Institute of High Energy Physics, Chinese Academy of Sciences, Beijing 100049, PR China;1. Central Research Institute of Structural Materials “Prometey”, Saint-Petersburg, Russia;2. Russian Research Center “Kurchatov Institute”, Moscow, Russia;1. Department of Nuclear, Plasma, and Radiological Engineering, University of Illinois at Urbana–Champaign, 104 South Wright Street, Urbana, IL 61801, USA;2. Oak Ridge National Laboratory, 1 Bethel Valley Road, Oak Ridge, TN 37831, USA;1. Department of Civil Engineering and Geological Sciences, University of Notre Dame, 156 Fitzpatrick Hall, Notre Dame, IN 46556, USA;2. Department of Chemistry, University of Iowa, Room E331 CB, Iowa City, IA 52242, USA;3. Department of Civil and Environmental Engineering, Southern Methodist University, P.O. Box 750340, Dallas, TX 75275, USA;1. Swerea-KIMAB, PO Box 55970, SE-10216 Stockholm, Sweden;2. Westinghouse Electric Sweden, SE-721 63 Västerås, Sweden
Abstract:
Spherical fuel elements of a high temperature gas-cooled reactor were disintegrated through a electrochemical method with NaNO3 as electrolyte. The X-ray diffraction spectra and total carbon contents of the graphite fragments were determined, and the results agreed with those from simulated fuel elements. After conducting the characterization analysis and the leaching experiment of coated fuel particles, the uranium concentrations of leaching solutions and spent electrolyte were found to be at background levels. The results demonstrate the effectiveness of the improved electrochemical method with NaNO3 as electrolyte in disintegrating the unirradiated fuel elements without any damage to the coated fuel particles. Moreover, the method avoided unexpected radioactivity contamination to the graphite matrix and spent electrolyte.
Keywords:
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