Spent Nuclear Fuel

Research Article| December 01, 2006 Spent Nuclear Fuel Jordi Bruno; Jordi Bruno 1Enviros Spain SL, Po Rubí 29-33, 08197 Valldoreix, Spain2Enresa-Enviros Waste Management and Sustainability Chair, Technical University of Catalonia (UPC), 08034 Barcelona, Spain E-mail: jbruno@enviros.biz Search for other works by this author on: GSW Google Scholar Rodney C. Ewing Rodney C. Ewing 3Department of Geological Sciences, University of Michigan Ann Arbor, MI 48109-1005, USA E-mail: rodewing@umich.edu Search for other works by this author on: GSW Google Scholar Author and Article Information Jordi Bruno 1Enviros Spain SL, Po Rubí 29-33, 08197 Valldoreix, Spain2Enresa-Enviros Waste Management and Sustainability Chair, Technical University of Catalonia (UPC), 08034 Barcelona, Spain E-mail: jbruno@enviros.biz Rodney C. Ewing 3Department of Geological Sciences, University of Michigan Ann Arbor, MI 48109-1005, USA E-mail: rodewing@umich.edu Publisher: Mineralogical Society of America First Online: 09 Mar 2017 Online ISSN: 1811-5217 Print ISSN: 1811-5209 © 2006 by the Mineralogical Society of America Elements (2006) 2 (6): 343–349. https://doi.org/10.2113/gselements.2.6.343 Article history First Online: 09 Mar 2017 Cite View This Citation Add to Citation Manager Share Icon Share Facebook Twitter LinkedIn Email Permissions Search Site Citation Jordi Bruno, Rodney C. Ewing; Spent Nuclear Fuel. Elements 2006;; 2 (6): 343–349. doi: https://doi.org/10.2113/gselements.2.6.343 Download citation file: Ris (Zotero) Refmanager EasyBib Bookends Mendeley Papers EndNote RefWorks BibTex toolbar search Search Dropdown Menu toolbar search search input Search input auto suggest filter your search All ContentBy SocietyElements Search Advanced Search Abstract The primary waste form resulting from nuclear energy production is spent nuclear fuel (SNF). There are a number of different types of fuel, but they are predominantly uranium based, mainly UO2 or, in some cases, metallic U. The UO2 in SNF is a redox-sensitive semiconductor consisting of a fine-grained (5-10 μm), polycrystalline aggregate containing fission-product and transuranium elements in concentrations of 4 to 6 atomic percent. The challenge is to predict the long-term behavior of UO2 under a range of redox conditions. Experimental results and observations from natural systems, such as the Oklo natural reactors, have been used to assess the long-term performance of SNF. You do not have access to this content, please speak to your institutional administrator if you feel you should have access.