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Division Spotlight
Decommissioning & Environmental Sciences
The mission of the Decommissioning and Environmental Sciences (DES) Division is to promote the development and use of those skills and technologies associated with the use of nuclear energy and the optimal management and stewardship of the environment, sustainable development, decommissioning, remediation, reutilization, and long-term surveillance and maintenance of nuclear-related installations, and sites. The target audience for this effort is the membership of the Division, the Society, and the public at large.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
Standards Program
The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
BWXT will scout potential TRISO fuel production sites in Wyoming
BWX Technologies Inc. announced today that its Advanced Technologies subsidiary has signed a cooperation agreement with the state of Wyoming to evaluate locations and requirements for siting a potential new TRISO nuclear fuel fabrication facility in the state.
L. H. Johnson, D. W. Shoesmith, G. E. Lunansky, M. G. Bailey, P. R. Tremaine
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 238-253
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32851
Articles are hosted by Taylor and Francis Online.
An integrated experimental approach to mechanistic studies of the leaching and dissolution of irradiated UO2fuel is described. The program includes an investigation of the solubility of the UO2 matrix under thermodynamically well-defined conditions, detailed measurements of the leaching and dissolution of irradiated fuel under simulated disposal conditions, and electrochemical measurements with a novel UO2 electrode to elucidate dissolution mechanisms. Initial experiments show that the solubility of UO2 under alkaline reducing conditions is relatively insensitive to temperature changes, that the leach rates of irradiated fuel are also not strongly temperature dependent, and that surface films on the UO2 fuel may play an important role in the dissolution process. Several aspects of the UO2 matrix dissolution process are now understood, and the approach taken has indicated where future work is needed.
