Iodine Capture and Storage
Abstract not provided.
Abstract not provided.
Abstract not provided.
Acta Crystallographica E. Structure Reports online
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Journal of the American Chemical Association
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
J. American Chemical Society
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
Abstract not provided.
International Nuclear Fuel Cycle Conference, GLOBAL 2013: Nuclear Energy at a Crossroads
The thermal processing of a proposed durable waste form for 129I was investigated. The waste form is a composite with a matrix of low-temperature sintering glass that encapsulates particles of AgI-mordenite. Ag-mordenite, an ion-exchanged zeolite, is being considered as a capture medium for gaseous 129I2 as part of a spent nuclear fuel reprocessing scheme under development by the US Department of Energy/Nuclear Energy (NE). The thermal processing of the waste form is necessary to densify the glass matrix by viscous sintering so that the final waste form does not have any open porosity. Other processes that can also occur during the thermal treatment include desorption of chemisorbed I2, volatilization of AgI and crystallization of the glass matrix. We have optimized the thermal processing to achieve the desired high density with higher AgI-mordenite loading levels and with minimal loss of iodine. Using these conditions, 625°C for 20 minutes, the matrix crystallizes to form a eulytite phase. Results of durability tests indicate that the matrix crystallization does not significantly decrease the durability in aqueous environments.
Proposed for publication in Industrial and Chemical Engineering Research.
Abstract not provided.
Abstract not provided.